ML20027B886
| ML20027B886 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, McGuire  |
| Issue date: | 09/27/1982 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20027B884 | List: |
| References | |
| NUDOCS 8209300264 | |
| Download: ML20027B886 (594) | |
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Revision Issbed Phil,1581 / .; Sudercedes NUREG-0452, Revision 3 [ ff L'Y U.S. Nuclear Regulatory Commission Of*1ce of Nuclear Reector Regulation 9
.. Q 8209300264 820927 PDR ADOCK 05000369 p PDR
FOREWORD , The following paragraphs briefly describe the applicability, format and imole-mentation of the Westinghouse Standard Technical Specification package. APPLICABILITY This Standard Technical Specification (STS) has been structured for the broadest possible use on Westinghouse piants currently being reviewed for an Operating License. Accordingly, the document contains specifications applicable to plants with (1) either 3 or 4 loops and (2) with and without loop stop valves. In addition, four separate and discrete containacnt specification sections are provided for ea'.n of the following containment type: /,tnosph?cic, Ice Condenser, Sub-Atmospheric, and Dual. Optional specifications are. crovid.9d for those features end systems which may be included in individual plant avsigns but are not generic in their scope of applicac N . Alternate specifications are provided in a limited number of cases to cover situations where aMernate specification requirements are neces::ary on a generic basis because of design differences. FORMAT The format of the STS addresses the categcr+4 required by 10 CFR .ind consists of six sections covering the areas of: Definitions, Safety Limits and Limiting Safety System Settings, Limitisig Canoiticas for : Operation, Surveillance Require-ments, Design Features, and Administrativi Contreis. Thc Limiting Conditions for Operation and Surveillance Requirements (Sections 3 cad 4) are presented in a combined format with each LCO appearing at the top of the page followed immediately by the applicable SursaiTla..ca. Reqdiremants. The combined Section O- 3/4 is further subdivided into tan iUcsections covering the areas of:
- 1. Reactivity Control,
- 2. Power Distribution,
- 3. Instrumentation,
- 4. Reactor Coolant System,
- 5. Emergency Core Cooling System:,
- 6. Containment Systems,
- 7. Plant Systems, O
- 8. Electrical
- 9. Refueling Operations, and
- 10. Special Test Exceptions.
The values of those parameters and variables which may vary because of plant design appear as either blanks or parenthesized numbers throughout the STS. The actual value for each par r.eter will be provided by individual applicants as appropriate for'their plants. The values in parentheses are for illustra-tion only. IMPLEMENTATION The implementation of the STS on an individual license application will proceed in three phases. The major steps within each phase are indicated below. Phase I The applicant should:
- 1. Obtain copies of the STS from the NRC.
- 2. Select the appropriate containment specification section and set aside the non-applicable containment sections and related bases.
- 3. Identify and mark those specifications not required because of plant design or other factors. Specifications within this category should be retained in position within the document package for
?ater review and discussion.
4 Ideatify those areas where specifications are required but are not provided in the STS.
- 5. Provide the applicable values of the parameters and variables identified by blanks or parentheses in the STS. This information must be consistent with the SAR and other supporting documents.
- 5. Provide the figures, graphs and other information required to complete the STS document package.
l Phase II
- 1. The Comission staff will review the information provided in tne marked up STS document package resulting from the ?hase I pre-paration.
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- 2. Applicant / staff meeting will be held to resclve noted differences of position and other related coments frem the applicant, vendor and A.E.
Phase III
- 1. The Comission will provic'e a Prcof and Review edition of the technical specification far final review by all parties based upon the resolution of coments and positions in Phase II.
- 2. Final coments and corrections will be incorporated into the doctanent as received.
- 3. The Technical Specifications will be issued by the Comission as Appendix "A" of the Operating License.
O O
i ' i I l I I l SECTION 1.0 DEFINITIONS I i I i I
DUKE POWER CCMPANY Form 00184 (6-81) __ m l DevdStation Unit File No. !l w.d) Subject -
* #eb I!
g By _ Date Sheet No._of Problem No. Checked By- Cate i j I
! 8
_l l ! ; j GASECUS RACWASTE TREATMENT SYSTEM
! 1. 4 ,, A GASEQUS RADWASTE TREATMENT SYSTEM is any systam designed and installec
- j. - - -
to recuce radioactive gaseous effluents by collecting primary cociant system _ . _ _ i offgases frem the primary system and providing for delay or holduo for tne purpose of recucing the total radioactivity orior to release to the environment. _ L _ _ _ _ _ _ _ _ -___._ _ _ _ . _ _ _ _ _ _ _ _ _
,. b -- 0FFSITE DOSE CALCULATICH MANUAL (CDCM)
^-
- 1. b. The OFFSITE 00SE CALCULATICN MANUAL snall contain the ethodolcqy and parametars used in the calculation of offsite doses due to aoicacttye gasexs and liquid effluents and in the calculation of gasecus anc liquic erfluent monitoring alarm / trip setpoints.
j. 1 i Il i _ ._1 1 l ' ' nj PROCESS CONTROL PROGRAM (PCP) --
'I .% ~L 1.& The PROCESS CONTROL PROGRAM shall contain the sampling, analysis, and formulation determination by which SOLIDIFICATICN of racioactive wastes from ---
i liquia systems is assurec. l ._ . _ _ _ . _ _ . _ - _ _ 5 i i,
~
PURGE - PURGING
.g -- ~'
1.ft PURGE or PURGING is the controlled process of discharging air or gas
; from a confinement to maintain temperature, pressure, humidity, concentration ,
II ,! or other operating condition, in such a manner that replacement air or gas is - .
,l required to purify the confinement. l I '
! , i ! i i i l
l , , , i 1 1 i SOLIDIFICATION 1 l n !
, 1.40- SOLIDIFICATICN shall be the conversion of radioactive wastes from liquid
[ systems to a homogeneous (uniformly distributed), monolithic, immobilized
! srlid with definite volume and shape, bounded by a stable surface of distinct _
j outline on all sides (free-standing). 4 1
! , SOURCE CHECK
]\qi 32 i 1.29 A SCURCE CHECK shall be the qualitative assessment of cnannel response j ~'wnen the enannel sensor is exposed to a radioactive source. I ; ! ! i i i i , I e l i
O 1.0 OEFINITIONS The defined terms of this section aopear in capitalized type and are applicable throughout these Technical Specifications. ACTION 1.1 ACTION shall be that part of a Specification which prescribes remedial measures required under cesignated conditions. ACTUATION LOGIC TEST
- 1. 2 An ACTUATION LOGIC TEST shall be the application of various simulated
! input combinations in conjunction with each possible inter 1cck logic state and verification of the required logic output. The ACTUATION LOGIC TEST shall include a continuity check, as a minimum, of output devices.
ANALOG CHANNEL OPERATIONAL TEST
- 1. 3 An ANALOG CHANNEL OPERATIONAL TEST shall be the injection of a simulated signal into the enannel as close to the sensor as practicable to verify 3
OPERABILITY of alarm, interlock and/or trip functions. The ANALOG CHANNEL
,/ OPERATIONAL TEST shall include adjustments, as necessary, of the alarm, inter-i lock and/or trip setpoints such that the setpoints are within the required range and accuracy.
AXIAL FLUX OIFFERENCE ! 1.4 AXIAL FLUX DIFFERENCE shall be the difference in normalized flux signals < ( between the top and bottom halves of a two section excore neutron detector. *
! CHANNEL CALIBRATION 1.5 A CHANNEL CALIBRATION shall be the adjustment, as ne m sary, of the channel such that it responds with the required range ana accuracy to known values of input. The CHANNEL CALIBRATION shall encomcass tne entire channel including the sensors and alarm, interlock and/or trip functions and may be performed by any series of sequential, overlapping, or total channel steps such that the entire enannel is calibrated.
l l CHANNEL CHECK , i I l 1.6 A CHANNEL CHECK shall be the qualitative assessment of channel behavior i during operation by observation. This determination shall include, where i possible, comparison of the channel indication and/or status with other I indications and/or status derived from independent instrument channels ' measuring the same parameter. W-STS 1-1 SEP I 51981
DEFINITIONS CONTAINMENT INTEGRITY
- 1. 7 CONTAINMENT INTEGRITY shall exist wnen:
- a. All penetrations required to be closed during accident conditions )
are either:
- 1) Capable of being closed by an OPERABLE containment automatic l l isolation valve system, or l
- 2) Closed by manual valves, blind flanges, or deactivated I automatic valves secured in their closed positions, except as provided in Table (3.5-1) of Specification (3.6.4.1).
- b. All equipment hatches are closed and sealed,
- c. Each air lock is OPERABLE pursuant to Specification (3.6.1.3),
- d. The containment leakage rates are within the limits of Specification (3.6.1.2), and
- e. The sealing mechanism associated with each penetration (e.g., welds, bellows, or 0 rings) is OPERABLE.
CONTROLLED LEAKAGE
- 1. 8 CONTROLLED LEAXAGE shall be that seal water flow supplied to the reactor coolant pump seals.
CORE ALTERATION
- 1. 9 CORE ALTERATION shall be the movement or manipulation of any component within the reactor pressure vessel with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATION shall not preclude completion of movement of a component to a safe conservative position.
DOSE EQUIVALENT I-131 1.10 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcurie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites." E - AVERAGE DISINTEGRATION ENERGY 1.11 I shall be the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for isotopes, other than iodines, with half lives greater than '!. minutes, making up at i least 95% of the total noniodine activity in the cuclant. I W-STS
- 1-2 SEP 151981
- -- -,, - - , . - - - . - . - - - - -- - n ,
OEFINITIONS ENGINEERED SAFETY FEATURE RESPONSE TIME 1.12 The ENGINEERED SAFETY FEATURE RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of perfoming its safety function (i.e. , the valves travel to their required positions, pump discharge l pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays where applicable. FREQUENCY NOTATION 1.13 The FREQUENCY NOTATION specified for the performance of Surveillance a C Requirements shall correspond to the intervals defined in Table 1.2. IDENTIFIED LEAKAGE 1.1+ IDENTIFIED LEAXAGE sh11 be:
- a. Leakage (except CONTROLLED LEAKAGE) into closed systems, such as pump seal or valve packing leaks that are captured and conducted to a simp or collecting tank, or
- b. Leakage into the containment atmosphere frca sources that are both O -
specifically located and known either not to interfere with the operation of leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE, or
- c. Reactor coolant system leakage through a steam generator to the secondary system.
!MASTERRELAYTEST
! /6 1.1& A MASTER RELAY TEST shall be the energization of each master relay and 7
o4 : verification of OPERA 8ILITY of each relay. The MASTER RELAY TEST shall include
;' ' a continuity check of each associated slave relay.
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'1 3 OPERA 8LE - OPERA 8ILITY
.. i6
, ii j 1.16 A system, subsystem, train, component or device shall be OPERABLE or V} "
i have OPERA 8ILITY when it is capable of perfoming its specified function (s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication er other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of perfoming their related support function (s). OPERATIONAL MODE - MODE I4 1.17 An OPERATIONAL MODE (i.e., M00E) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.1. PSTS 1-3 SEP 151881
DEFINITIONS PHYSICS TESTS ze i 1.ie PHYSICS TESTS shall be those tests performed to measure the fundamental l nuclear characteristics of the reactor core and related instrumentation ' (1) described in Chapter (14.0) of the FSAR, (2) authorized under the provisions of 10 CFR S0.59, or (3) othemise approved by the Commission. PRESSURE BOUNDARY LEAKAGE
/
1.19 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a nonisolable fault in a Reactor Coolant System component body, pipe wall, or vessel wall. f- , -) QUADRANT PCWER TILT RATIO
,y"'- zu 1.29 QUADRANT POWER TILT RATIO shall be the ratio of the maximum upper excore
', 3 detector calibrated output to the average of the upper excore detector cali-
, brated outputs, or the ratio of the maximum lower excore detector calibrated I >' output to the average of the icwer excore detector calibrated outputs, wnichever is greater. With one excore detector inoperable, the remaining three detectors shall be used for computing the average.
RATED THEMAL POWER O 25 1.21 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of MWt. REACTOR TRIP SYSTEM RESPONSE TIME 2G 1.GE The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored paramster exceeds its trip setpoint at the channel sensor until loss of stationary gripper coil voltage. l REPORTABLE OCCURRENCE
;7
- 1. 2-3 A REPORTABLE OCCURRENCE shall be any of those conditions specified in Specifications 6.9.1.8 and 6.9.1.9.
O pSTS 1-4 SEP 151981 l l
O OEFINITIONS
/L. w 4dMk0 BUILDING INTEGRITY J., .u wr 1.2+ -SMhD BUILDING INTEGRITY shal1 exist whon:
a :.
- a. Each door in each access opening is closed except when the access opening is being used for normal transit entry and exit, then at least one door shall be closed, am. wv. r
- b. The 4hield M"j.s sr, .,.M 41tra44en. system is OPERABLE, and
- c. The sealing mechanism associated with each penetration (e.g. , welds, bellows, or 0 rings) is OPERABLE.
SHUTCOWN MARGIN l 1.25 SHUTCCWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present conoition assumingy
- 2. 5 change-in part-1ength: rod-position,, and E 411 full length rod cluster assemolies (shutdown and control) are O' '
fully inserted except for the single rod cluster assembly of hignest reactivity worth wnich is assumed to be fully withdrawn. SLAVE RELAY TEST 3c f 1.2fr A SLAVE RELAY TEST shall be the energization of each slave relay and verification of OPERA 8ILITY of each relay. The SLAVE RELAY TEST shall include a continuity check, as a minimum, of associated testable actuation devicas. D '/ 'Z,% sue cv~ STAGGERED TEST SASIS cn - lC 3 1.27 A STAGGERED TEST BASIS shall consist of:
- a. A test schedule for n systems, subsystems, trains, or other designated components obtained by dividing the specified test interval into n equal subintervals,
- b. The testing of one system, subsystem, train, or other designated component at the beginning of each subinterval.
THERMAL POWER
- 9 7 1.29- THERMAL POWER shall be the total reactor core heat transfer rate to tne O' reactor coolant.
PSTS 1-5 SEP 15 51
OEFINITIONS f / TRIP ACTUATING DEVICE OPERATIONAL TEST J5 1.09 A TRIP ACTUATING DEVICE OPERATIONAL TEST shall consist of operating the Trip Actuating Device and verifying OPERABILITY of alarm, interlock and/or trip functions. The TRIP ACTUATING DEVICE OPERATIONAL TEST shall include adjustment, as necessary, of the Trip Actuating Device such that it actuates at the required setpoint within the required accuracy. UNIDENTIFIED LEAKAGE 30 1.36 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE or CONTROLLED LIAKAGE. O l \
\
9: l PSTS 1-6 SEP 151981
- - - - - - - - - , . - - _ - - - - - , - , - - - - - - - - _ - - - _ _ _ _ - - w=w-- -
O DEFINITIONS VENTILATION EXHAUST TREATMENT SYSTEM J7 1.30- A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radiciodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases througn charcoal adsorcers and/or HEPA filters for the purpose of removing iocines or particulates from the gaseous exhaust stream prior to the release to the environment. Engineered Safety Features (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM comoonents. VENTING 77
- 1. M VENTING is the controlled precess of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or otner coerating condition, in suca a manner that replacerent air or gas is nct proviced or required during VENTING. Vent, used in system names, does not imply a VENTING process, v)
O. McGUIRE - UNIT 1 1- 7 UtT7 _
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. _ _ -_ . __ _ ,m . _ _ _ . _
O TA8tE 1.1 OPERATIONAL M00ES REACTIVITY % RATED AVERAGE COOLANT MODE CONDITION, K THERMAL POWER" TEMPERATURE gf
- 1. POWER OPERATION > 0.99 > 5% > 350*F
- 2. STARTUP > 0.99 1 5% > 350*F
- 3. HOT STAND 8Y < 0.99 0 > 350*F
- 4. HOT SHUTDOWN < 0.99 0 350*F
> 200*F> T**9
- 5. COLD 51!UTD0hN < 0.99 0 1 200*F
- 6. REFUELING ** 1 0.95 0 1 140*F 0
- Excluding decay heat.
** Fuel in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.
O PSTS 1-5 AUG 7M l l - _ _ _ _ _ _ _ , _ _ . . _ _ _ _ _ _ _ _ _ - . _ _ _ _ _ _ _ _ . _ _ _ _ _ - . _ _-- , _-
O TABLE 1.2 FREOUENCY NOTATION NOTATION FREOUENCY S At least once per 12 hours. O At least once per 24 hours. W At least once per 7 days. M , At least once per 31 days Q At least once per 92 days. SA At least once per 184 days. R At least once per 18 months. S/U Prior to each reacter startup. N.A. Not applicable, u ..,( /e 7L J' p . c, rv <b f iz/u s c. . l i O\
,y-STS 1,y 9 y 1979 i
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SECTION 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS I I e m -- , ---. .. v---r , _-. _ --..--% -- ----,---,m-----. - - , - - , , - . . - . _ , - - . - - - - , - . ,-.-,y- - - .-- ---, --, , --
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2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 SAFETY LIMITS REACTOR CORE 2.1.1 The combination of THERMAL POWER, pressurizer pressure, and the highest shall not exceed the limits shown in operating Figures 2.1-1 loop coolant and temperature 2.1-2 for n and n-l (T*Y8c)p operation, respectively. APPLICA8ILITY: MODES 1 and 2. ACTION: Whenever the point defined by the combination of the highest operating loop average temperature and THERMAL POWER has exceeded the appropriate pressurizer I pressure line, be in HOT STAND 8Y within 1 hour, and comply with the require- ! ments of Specification 6.7.1. . --
- ~ - "
a n ,.w. . REACTOR COOLANT SYSTEM PRESSURE 2.1.2 The Reactor Coolant System pressure shall not exceed 2735 psig. APPLICA8ILITY: MODES 1, 2, 3, 4, and 5. ACTION: MODES 1 and 2 Whenever the Reactor Coolant System pressure has exceeded 2735 psig, be in HOT STAN08Y with the Reactor Coolant System pressure within its limit within i hour, and comply with the requirements of Specification 6.7.1. MODES 3, 4 and 5 Whenever the Reactor Coolant System pressure has exceeded 2735 psig, reduce the Reactor Coolant System pressure to within its limit within 5 minutes, and comply with the requirements of Specification 6.7.1. f t O - W-STS
- 2-1 SEP 2 8 to81 I .. .- _
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0 0.2 0.4 0.6 0.8 1.0 1.2 FRACTION OF RATED THERMAL PCWER FIGURE 2.1 1 REACTOR CORE SAFETY LIMIT. FOUR LOOPS IN OPERATION McGUIRE - UNIT 1 2-2 UNU % n --
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O Figure 2.1-2 left blank pending the NRC aporoval of three loop operation O McGUIRE - UNIT 1 2-3
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. . . .. . .._ .f ._.- -
. . _ _ . . ..._ ... _. .gw . [ %. .. .w.___a._.._.
_ t._. .... ._ _.,<,. . _.. ... . t. .... = ___.t_ _ . - ._
._ ... . 2250 PSIA,,
. ._ . . t;. ._._-._ . _
.tx._. _._._._.._ _.
.. . - - . . -. - l m + - - - -- - 2._. -f _ -
.1._ . . . _ . . . - - . . .
_._t._.___..%_..,<.---
. _-. t:..
- . _._.,_ _._ p.
t_... ...-.. e g _ . __~ .
% .m .. - - . . _ _
.....t_......s._............_.._._%.. . . . . __ ._%. .
( . .. . ._ .._. . . . . . .. . . . _ _.
....._._gs ,
.- . -. s. .. __
_ . _ . . _. - ._. . ._~ t.. - _ . .. .. _. _ . . w
. _.t..... ..__. .
. - .t...........t.
/.. . . . .t .. - . . .. ._.._..
- u. o,.20
. w
__. .t .... m
. . _ . . _ _ _ . _ . _ ._m_ .v,.__
c . .. .. .. .. _ . . t. r _. . 4_._
..t.. . .
. _ 4._.....
. A. . , _ ._
. . . _. .,_..-- . _ _ x_
.. _w__;.. __ _ ._. . .....
.t - 2000 pgggr . . . a> .w_..__ _ _ . - - _..,_
._.....g...-. . . r. y. .
ei
. . .. . .. . _ . . . . .. 4 . . .
4 . .. .. .. .. ..g.. .. ..,. .
.[...-.....s.._......
.. m..g._....g... .... ..
7 ... .
- g. . . .. ..+ .
.: -l
>" / THIS FIGU 80R ILLUSTRATION ONLY s .$ '. ....'.~ !. : , . . . . f.
*. - . t.* ;
a FOR OPERAT10N
, DO NO
. t/. ,.p ..
.. 1t to o ,.
. .l.
.l
.t c: 600 .t
, i f .J
- g. . . t . . . 1
. . . ., . v...,.. .. . . _
. 3 /00 PSIAy .1 ., - t ._ . . " _ . _ , . . , . - -+ - . . ~ . . ..
s g. .
...l... ..).
. . _ . .......t... . _. . L.
.t. . . . . . . . . . _ L._ . .
.. . . l ...
.t. _ _ . . ..t....
. . t. _ .. . . .. .. . .. . . .
. . .I . .l..... .s . .
A EFTAB LE _6. .... . . . . t .
.t.. ......
- . ..... .r.
.. .,. OPERATION . .-
.s "_ .-..- ". L.
. . . t. . ._ . .. ....
........N. . .. ,...
t...
. r . . . ......
. .I.
- r. .
. . ..t..l .,.
....N.. ...... ..N..
- e. . , .. . __ . . . . . . . .
. _. t . -
. .I...
.I.
i
.... .. . ... . x. y.. ..... .. ..
, .. .t.
.t.
..L.._.
0 0.2 0.4 0.6 0.8 FRACTION OF RATED THERMAL POWER FIGUR E 2.12 REACTOR CORE SAFETY LIMIT - THREE LOOPS IN OPERATION _y u m. i= y Su wc.../o(' b ,, ,m .s n s ,c y p .e , W-STS _ 23
j l SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.2 LIMITING SAFETY SYSTEM SETTINGS REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS 2.2.1 The reactor trip system instrumentation and interlocks setpoints shall be set consistent with the Trip Setpoint values shown in Table 2.2-1. APPLICA8ILITY: As shown for each channel in Tacle 3.3-1. ACTION: With a reactor trip system instrumentation or interlock setpoint less conserv-ative than the value shown in the Allowable Values column of Table 2.2-1, declare the channel inoperable and apply the applicable ACTION statement requirement of Specification 3.3.1 until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value. O O pSTS , 2-4 SEP 1 5 79
o l 0 0 i TABLE 2.2-1 l If REACTOR TRIP SYSlEM IhSTRUMENTATION TRIP SETPOINTS "4
" TRIP SETPOINT ALLOWA8tE VAltlES FUNCTIONAL UNIT
- 1. Manual Reactor Trip Not Applicable Not Appilcable ,
- 2. Power Range, Neutron Flux Low Setpoint - 1 (25)% of RATED Low Setpoint - 1 (26)% of RATED THERMAL POWER THERMAL POWER High Setpoint 1 (109)% of RATED H10h Setpoint - 1 (110)% of RATED THERMAL POWER TilERNAL POWER {
- 3. Power Range, Neutron Flux, 5 (5)% of' RATED THERMAL POWER with 5 (5.5)% of RATED THERMAL POWER High Positive Rate a time constant 1 f$) seconds with a time constant 1 M seconds g- a f.5- .2
- 4. Power Range, P.eutron Flux, < Q)% of RATED THERMAL POWER with < ( M )% of RATED THERMAL POWER I H19h Negative Rate a time constant 1 (t) second>
! m 2 with a time constant 1 (A+) seconds
] ln 5. Intermediate Range, Neutron 1 (25)% of RATED THERMAL POWER 1 (~20)% of RATED THERMAL POWER i Flux l 5 5 l 6. Source Range, Neutron Flux 1 (10 ) counts per second 1 (1.3 x 10 ) counts per second
- 7. Overtemperature AT See Note 1 See Note 3 i
) 8. Overpower AT See Note 2 See Note 3 .l' i }9'ff /175 ,
- 9. Pressurizar Pressure--Low 1 (486!ir) psig 1 (4865) psig i 10. Prc.surizer Pressure--High 1 (2385) psig 1 (2395) psig i
- 11. Pressurizer Water Level--High 5 (92)% of instrument span 5 (93)% of instrument span
]
- 12. Loss of Flow 1 (90)% of desi0n flow per loop * ~
> (89)% of design flow per loop *
- 97,Do j
S
- Design flow is g $ gpa per loop.
1 i 3 I i i
Y TAllLE 2.2-1 (Continued) ti REAC10R TRIP SYSTEM INSIRUMENIA110H 1 RIP SElPOINIS FUNCTIONAL UNIT TRIP SETPOINT All0WABLE VALUES 413'j'S,1J3af,Ghowrbowibpya$e'r tevel-- sf3 [D% 9f nar[r 'w generator rangd ins rtununt. g.{8J%,)'Jf.ndrrowrange'lysgrl'qnt-s an-bach st6a span each' steam Ifener[ tor I M,([aferv t, rb , np $#
. f, par 2merth span--cac[r6w 6 13 sttpr jf2f%)ip yan0riteam>Jencea(or narrow angg-jdsJry ment spah--cach s] team geherator, e p1 ~ en ' di
'sm I L 0 4 $ ER
/> W. Undervoltage-Reactor 1 (476&) volts each bus 3/10) volts each hus Coolant Pumps Sv/L 1 (Ec'/0 m N 16'. Underfrequency-Reactor > (Sht) Ilz - each bus 1 (f>M) Itz each bus
& Coolant Pumps f6, ef rcy
/f Fr. Turbine Trip eff 1,4.
A. Low Trip System 1 (6003 psi 0 1 (800) psig Pressure B. Turbine Stop Valve 1 (1%) open 1 (1%) open Closure
/018. Safety Injection Input Not Applicable Not Applicable from ESF
'r o tl I p'd ao ca rb G 9 9 --
. l ' l ' .ll I
_ ~ O , i (
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3 o , tRo0 Et 0 s R7 O P'[ I A e W 0W 1 . u s M s 0 O y R f L u R l l mPl tE p E i t p S f o rL a rawO h c h l l ie Eg l E " fA enP a c - U L I U Mna aRi pL d a e. l e ' I. E D I a in v A 6 aEl sA s b I t V 1 pi l sl gfR M t h a c A r d, l t W'R#{ig E noE o z i w l I p fDi l l v. i l l p f t e l l Doo oE s%I . r S A W kl %A e I a9
.D 6
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j i! ij' ,lI O D D E E T T A e A e S s R ne R ne E p i r i r U n f bu D f bu e e L a oR rs ER oR rs l l A E us TE E us b b V I %W Te AW %W T e a a I 1O rt RO 1O rt c c E PPn P L B
'01 1P 5L T
R el e f oL 1P
<E PP n I
R el e i l p i l p A A sa A A sa p p W x ,M %l v %M ,M %l v A A S 0 %R 1 ui76R pu %R 1 ui I N l l 6 9E l i 1 m q93 E l i 9E l 1 pu mq t o t o l A 1 >T <IE 5T >Ti 5I E N N 0 P I L S P I R e e
)
l T s p ne ne ( i r i r e N m bu D bu e e u O T a R rs ER R rs l l n I N DE us 1E DE us b b i T I 0 EW T ert . AW EW T e a a t A O 1 TO RO TO rt c c O _ n I P - AP PP n P AP PP n i i o N 1 0 R T e f R I e l l E E 1 L R el oL L Rel p p (C M S fA sa A fA sa p p x oM %l oM 0 ui v9 %5R M t
%l v A A 1 R P R R 0 ui
- T I 1
%E 1 pu43E aq %E 1 pu mq t t 2 S R 0i l l i 0i l o o 2
. N I
T 1 1 T <TE <T 1T 5I E N N E M L E B T A S T Y S , P n e o r I r u R 8 t s T - u s R n P e e N r O s o , P T k r x e C c t s u g r A o u p l n e E l e i F a b R r N r R m e T n a t e o r h n g r r e C I n o t w s a t t t u o e r c m R c u u e P s e i e a p p N l k g t e e n n t u a o s t R I I e n p e L S y a i6 r-7 0 3 g n i0 a r p o1 J B p d- eP 1 1 a p- i eP w - - R tP e p r i m o , P P e n i 1 T r r , Pk r S , i r I T ex c e x b3 T c N U r t u wo w wu r1 i o nl ol . . o ol u- r t IF LB a b P L F. TP o a L t t m A c c o N a O a t O e . . . . . e u I R A B C D E R A T C N . U 0 2 F 2 /' M
/ 2 y '"
?
$C3 e w ~O 4
l l
i
! TABLE 2.2-1 (Continued)
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS
]
NOTATION 1 1+Tb2 1 NOTE 1: Overtemperature AT (y , , 3) 1 AT, {Ky -K 2 Il + r 5)[T(y , 3 3)-T'] + K3 (P-P') - f y(AI)) 1 where: = Lag compensator on measured AT 3 1 ty
= Time constants utilized in the lag compensator for AT r3 y = (2) secs.
AT = Indicated AT at RATED TilERMAL POWER
/.C752 Ky Ap (1c14)
, 7 m K 2
=
-(0:009) E #/3 4 1+ISp
=
y, S The function generated by the lead-lag controller for T,,g dynamic compensation 1 2 ' & '3
=
Time constants utilized in the lead-lag controller for Tav0' '2 = secs., 13 = (4) secs. T = Average temperature F 1 = y,73 Lag compensator on measured T,yg I 4
= Time constant utilized in the measured T avg lag compensator, 14 = (2) secs.
y C6 5. 2 5 T' 5 (578 # F) Reference T avg
- co K =
( N 3) 3 [a C. dis' C t/ 7 O O O
O - lADIE 2.2-1 (Continued)
'T REACIOR 1 RIP SYSifM INSIRUMENIAIION 1 RIP SLIPOINIS ]
NOTATION (Continued) , NOTE 1: (Continued) P = Pressurizer pressure, psig < P' = (2235) psig (Nominal RCS operating pressure) S = Laplace transform operator. sec'I and f (AI) is a function of the indicated ditterence between top and bottom detectors i of the power range nuclear ton chambers; with gains to be selected based on measured ' instrument response during plant startup tests stich that: 3(,, Li (i) for qt"9b between ( .30) percent and (e A) percent, yf (al) s 0, where qt and g 4 are percent RAIED TilERMAL POWER in the top and bottom halves of the core i respectively, and q +q is total M i in percent of RAHD THN NR. t b M (ii) for each percent that the magnitude of q, q' exceeds (-36) percent, the Al trip g - setpoint shall be aistomatically reduced by (0.tt9i.3 percent of its value at RAl[D lilLRMAL POWLR.
'7. 5 (iii) for each percent that the magnitude of qt gh exceeds (*A) percent, the Al trip setpoint shall be distomatically reduced by (0.00) percent of its value at RAlED lilERMAL POWER. J./R3 E
o an
I I i
'T 1ABtf 2.2-1 (Continued) y itfACIOR IRIP SYSILH INSTRUHtNTA110N lillP Sill'0INIS N0lAll0N (Cont.inued) 1 15b I I NOTE 2: Overpower AI (g , g 3) i AI9 {K4 -K 1 g (g , ,53) (g , ,43) I -K6 III Ie r 45) ~ I"l ~ # 2IAIII I
Where: j , g
=
as defined in flote 1 1 1
=
as defined in flote 1 Al g = as defined in Note 1
= / C 7 0.9 K
4 &MS T K =
'e 9 (0.02/"l) for increasing average tesaperattare and (0) for decreasing average tentperattire t 5 9 =
3, S line f unct ion generated by Llie rate-lag controller for I tlynamic 5 compensation 1 = 5 9 lime constant utilized in the role-lag controller for 1,y ,i s = (M) wcs. I = g, 3 as defined in Note 1 1 4 = as defined in Note 1
- c. cen c 'f u
K 6 = .4tLUG1l) f or I > I"6 and IU) K I I I" I'"' E T = as defined in flote 1
- F 2 W. :L w I" =
40 (1 Y/&4*f) Ref erence I at itAllD lillitful l'0WLR 9 S = as defined in Note 1
=
(2(al) 0 for all Al e 9 8 --
i i 1 t J l 1 i l - TABLE 2.2-1 (Continued} If M u REAC10R TRIP SYSIEM INSlRLMNIA110N 1 RIP SEIPOINIS i i NOIATION (Continued) I e i Note 3: The channel's maximum trip point shall not exceed its computed trip point by more than 2 percent. i I E i l 1 l l 4 1 7
- C l
u 1
)
U 4 C 1 G3 ce SD 4
,--y- _ w - - -,
BASES FOR SECTION 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS l
l 1 NOTE The BASES contained in succeeding pages summarf:e the reasons for the Specifications in Section 2.0, but in accordance with 10 CFR 50.36 are not part of these Technical Specifications. O O = '"
_ . . _ _ . . _ _ _ _ _ ._. _ _ l l l l 2.1 9FETY LIMITS ! BASES 2.1.1 REACTOR CORE The restrictions of this Safety Limit prevent overheating of tne fuel and possible cladding perforation which would result in the release of fission ! products to the reactor coolant. Overheating of the fuel cladding is prevented by restricting fuel operation to within the nucleate boiling regime where the heat transfer coefficient is large and the cladding surface temperature is slightly above the coolant saturation temperature. Operation above the ucper boundary of the nucleate boiling regime could result in excessive cladding temperatures because of the onset of departure frem nucleate boiling (DNB) and the resultant snarp recuctica in heat transfer coefficient. ON8 is not a directly measurable parameter during operation and therefore THERMAL PCWER and Reactor Coolant Temperature and Pressure nave been related to ON8 through the W-3 correlation. The W-3 DNS correlation nas been developed to predict the CNB flux and the location of CNB for axially uniform and non-unifor's heat flux distributions. The local DN8 heat flux ratio, DNBR, defined as the ratio of the heat flux that would cause DN8 at a particular core location to the local heat flux, is indicative of the margin to CNB. The minimum value of the ONBR during steaoy state operation, normal operational transients, and anticipated transients is limited to 1.30. This value corresponds to a 95 percent probability at a 95 percent confidence level that ON8 will not occur and is chosen as an approoriate margin to DN8 for all operating conditions. The curves of Figures (2.1-1) and (2.1-2) show the loci of points of THERMAL POWER, Reactor Coolant System pressure and average temperature for which the minimum DNBR is no less than 1.30, or the average enthalpy at the vessel exit is equal to the enthalpy of saturated liquid. N These curves are based on an enthalpy hot channel factor, F H, of 1.59 and a reference cosine with a peag of 1.55 for axial power shape. A?! allowar is included for an increase in Fh at reduced power based on the expression: Fh=1.55(1+0.2(1-P)] where P is the fraction of RATED THERMAL POWER These limiting heat flux conditions are higher than those calculated for the range of all control rods fully withdrawn to the maximum allowable control rod insertion assuming the axial power imbalance is within the limits of the f (delta I) function of the Overtemperature trip. When the axial power im) balance is not within the tolerance, the axial power imbalance effect on the Overtemperature delta T trips will reduce the setpoints to provide protection O consistent with core safety limits.
}{-STS *8 2-1 ygg 7 3 ;g7g
SAFETY LIMITS BASES 2.1.2 REACTOR COOLANT SYSTEM PRESSURE The restriction of this Safety Limit protects the integrity of the Reactor Coolant System from overpressurization and thereby prevents the release of radionuclides contained in the reactor coolant from reaching the containment atmosphere. The reactor pressure vessel and pressurizer are designed to Section III of the ASME Code for Nuclear Power Plant which permits a maximum transient pressure of 110% (2735 psig) of design pressure. -The Reads Caelect Sy::::
;'ptng, ,el es :nd 'ftting;, ace d;;igned te A::: S 27.'
- - --Ed4t4 e
.which p . n a m ir,w. tr;n;f: t precrure f 120% (2005 prig 4-.af component-
-design-pre::ure.- The Safety Limit of 2735 psig is therefore consistent with the design criteria and associated code requirements.
The entire Reactor Coolant System is hydratested at 3107 psig,125% of design pressure, to demonstrate integrity prior to initial operation. O O W-STS B 2-2 MAR Ig 7g79
. _ .~
^
O 2.2 LIMITING SAFETY SYSTEM SETTINGS BASES 2.2.1 REACTOR TRIP SYSTEM INSTRUMENTATION SETPOINTS The Reactor Trip Setpoint Limits specified in Table 2.2-1 are the nominal values at which the Reactor Trips are set for each functional unit. The Trip Setpoints have been selected to ensure that the reactor core and reactor l coolant system are prevented from exceeding their safety limits during normal operation and design basis anticipated operational occurrences and to assist the Engineered Safety Features Actuation System in mitigating the consequences of accidents. The various reactor trip circuits automatically open the reactor trip breaners whenever a condition monitored by the Reactor Protection System reaches a preset or calculated level. In addition to redundant channels and trains, the design approach providas a Reactor Protection System which monitors numerous system variables, therefore, providing protection system functional diversity. The Reactor Protaction System initiates a turbine trip signal whenever reactor trio is initiated. This prevents the reactivity insertion that would otherwise result from excessive reactor system cooldown and thus avoids unnecessary actuation of the Engineered Safety Features Actuation System. O Operation with a trip set less conservative than its Trip Setpoint but within its specified Allowable Value is acceptacle on the basis that the l difference between each Trip Setpoint and the Allowable Value is equal to or less than the drift allowance for all trips including those trips assumed in the safety analyses. Manual Reactor Trio e The Reactor Protection System includes manual reactor trip capability. Power Rance. Neutron Flux l l In each of the Power Range Neutron Flux channels there are two independent l bistables, each with its own trip setting used for a high and low range trip l setting. The low setpoint trip provides protection during subcritical and icw power operat1ons to sitigate the consequences of a power excursion beginning from low power, and the high setpoint trip provides protection during power l operations to mitigate the consequences of a reactivity excursion frem all I power levels. O pSTS B 2-3 l HP A 5 M
LIMITING SAFETY SYSTEM SETTINGS BASES Power Range. Neutron Flux (Continued) ThelowsetpinttripmaybemanuallyblockedaboveP-10(apowerlevel of approximately 4Wpercent of RATED THERMAL POWER) and is autcmatically reinstateri beow the P-10 setpoint. Power Range, Neutron Flux. High Rates The Power Range Positive Rate trip provides protection against rapid flux increases which are characteristic of a rupture of a control rod drive housing. Specifically, this trip complements the Power Range Neutron Flux High and Low trips to ensure that the criteria are met for rod ejection from mid power. The Power Range Negative Rate trip provides protection to ensure that the minimum DNBR is maintained above 1.30 for control rod drop accicents. At high power a single or multiple red drop accident could cause local flux peaking which, when in conjunction with nuclear power being maintained equivalent to turbine power by action of the automatic rod control system, could cause an unconservative local DNBR to exist. The Power Range Negative Rate trip will prevent this from occurring by tripping the reactor for all single or multiple dropped rods. Intermediate and Source Range, Nut.ltar Flux The Intermediate and Source Range, Nuclear Flux trips provide reactor core protection during reactor startup to mitigate the consequences of an uncontrolled rod cluster control assembly bank withdrawal from a subcritical condition. These trips provide redundant protection to the low set;oint trip of the Power Range, Neutron Flux chgnnels. The Source Range channels will initiate a reactor trip at about 10 3 counts per second unless manually blocked when P-6 becomes active. The Intermediate Range channels will initiate a reactor trip at a current level equivalent to approximately 25 percent of . RATED THERMAL POWER unless manually blocked when P-10 becomes active. No 1 credit was taken for operation of the trips associated with either the Intermediate or Source Range Channels in the accident analyses; however, their I functional capability at the specified trip settings is required by this ! specification to enhance the overall reliability of the Reactor Protection l ! System. O W-STS B 2-4 SEP 151981 1
. .l .
~ ^
_ _ _ _ . , 7 ~ --. - l l LIMITING SAFETY SYSTEM SETTINGS BASES Overtemperature ai The Overtencerature delta T trip provides core protection to prevent ON8 for all comoinations of pressure, power, coolant temperature, and axial power distribution, provided that the transient is slow with respect to piping transit delays from the core to the temperature detectors (about 4 seconds), and pressure is within the range between the Pressurizer high and low pressure trips. The setpoint is automatically varied with 1) coolant temperature to correct for temperature induced changes in density and heat capacity of water and includes dynamic compensation for piping delays from the core to the loop temperature detectors, 2) pressurizer pressure, and 3) axial power distribution. With normal axial power distribution, this reactor trip limit is always below the core safety limit as shown in Figure 2.1-1. If axial peaks are greater than design, as indicated by the difference between top and bottom power range nuclear detectors, the reactor trip is automatically reduced according to the notations in Table 2.2-1. bPTIONAL OR PI. ANTS PERMIT N-iLOOP'OPERATCN ,3 ll
, !' I f 'j /?
O '/ f: l f peration with' a reactor coolant loop o.uti of seryica'below the (n) loop , P-8 etpoint does not req 6 ire! reactor protection system setpoint, modification. becausar the' P,-8/setpoint.and . associated trip will prevent. 048 duripg (n 1)- , l (n-1,) loopf l ,floop operation,/ exclusive l /of the Overtemperature f de.lta T setooint.Pperat,f on'/a
, input ,to t) j 'ljKJj/fts tfo f ri-1)/l,e valverterature,de,ltaTchannels/anciraisingtheP-8jietooint oop ,0 In th[s l mode of/ cperat on,uhe! ?-8 /
Trip functions V as dJiigh Neutron Elux ytrip at\thevreducedtpow/interloc.Vand
/ 1 er l'evel. *
\./
Overpower ai The Overpower delta T reactor trip provides assurance of fuel integrity, e.g. , no fuel pellet cracking or melting, under all possible overpower conditions, [ limits the required range for Overtemperature delta T protection, and provides l a backup to the High Neutron Flux trip. The setooint is automatically varied l with 1) coolant temperature to correct for temperature induced changes in density and heat capacity of water, (and) 2) rate of change of temperature for dynamic compensation for piping delays from the core to the loop tamoerature detectors, (and 3) axial power distribution,) to ensure that the allowable heat generation rate (Kw/ft) is not exceeded. The overpower AT trip provides protection to mitigate the consequences of various size steam breaks as reported in WCAP 9226, " Reactor Core Response to Excessive Secondary Steam Break." O M-STS B 2-5
, SEP 15 !C81
i LIMITING SMETY SYSTEM SETTINGS - BASES ! Pressurizer Pressure In each of the pressure channels, there are two independent bistables, l each with its own trip setting to provide for a high and low pressure trip l thus limiting the pressure range in which reactor operation is permitted. The low setpoint trip protects against low pressure which could lead to ONB by tripping the reactor in the event of a loss of reactor coolant pressure. On decreasing power the lay,setpoint trip is automatically blocked by P-7 (a power level of approximately"M percanj of RATED THERMAL POWER with turbine impulse chamber pressure at approximately/ W percent of full power equivalent); and on increasing power, automatically reinstated by P-7. The high setpoint trip functions in conjunction with the pressurizer relief and safety valves to protect the Reactor Coolant System against system overpressure. Pressurizer Water Level The pressurizer high water level trip is providec to prevent water relief through the pressurizer safety valves. On decreasing power the pressurizer
~
high water leyel trip is automatically blocked by P-7 (a power level of // approximately".M percent of RATED jf THERMAL POWER with a turbine impulse chamcer pressure at approximately. W percent of full equivalent); and on increasing power, automatically reinstated by P-7. Loss of Flow The Loss of Flow trips provide core protection to prevent CNB by mitigating the consequences of a loss of flow resulting from the loss of one or more reactor coolant pumps. 57 %, // On increasing power above P-7 (a power levelhf approximataly M percent of RATED THERMAL POWER or a turbine impulse chambhr pressure at approximately
// -M percent of full power equivalent), an automa (c reactor trip will occur if the flow in more than one loop drops below ( of nominal full loop flow.
Above P-8 (a power level of approximately percent of RATED THERMAL POWER) pj;; an automatic reactor trip will occur if t flow in any single loop drops belV(.9s percent) of cominal full loop f w. Conversely on decreasing power between P-8 and the P-7 an automatic reactbr trip will occur on loss of flow in more than one loop and below P-7 the trip nction is automatically blocked. 4 '/ h 9 W-STS B 2-6 SE? i 51981
- - . . ~ . _ _ ____
0 LIMITING SAFETY SYSTEM SETTINGS BASES Loss of Flow (Continued) e , , OPTIONAL FOR PLANTS PERMITTED N-1 LCOP OPERATICN
- // y .. -
y / , '/ ,, { .'!Thej -8 setpofpt t p wi ' pre, vent theJnipimLe value o the ONBR.from f P cipated, transients going.be<1ow 1'.30 dyrin erma operational /tr,'ansients/and'
, wnen (n-1) loops are i o is' adjusted to thel va e/peratfon'/and specifi'ed for all"the/0y(ertesp' loops' inr operadion.' erystdre/ 'With eltfa th4 .T! trfp setpoint Overtemperature delt Ttr.ip/etpointadju#sted, todhe /vsluelspecified, for 7
~
(n-1)jloop operatib the/P-8 trip at (75%)'RATEDiTHERMAL.PCWER willeprevent th'e/ miniwum value .cf the'0NBR / from gofng belos 1.30/ dkring normal operational transifnts and,'antjcipated tra'nsierrts with (6-1) loops in operation. .- v a v ' s s ;/ Steam Generator Water Level The steam generator water level low-low trip protects the reactor from loss of heat sink in the event of a sustained steam /feecwater ficw mismatch resulting from loss of rormal feedwater. The specifiea setpoint provides , allowances for starting delays of the auxiliary feecwater system. i StiIm/FebdQater'Fld) MisNtIhbnd fow-St9am.GeiRerat'br Vadr Level,
, ,s . ,- ,- ,z, - i ,- ;, 9 -
, , , ,; /
- ; u /,/ , team
'.The ,c s /feedwater ' flow mismatch 'in co;focidence with ,a'steama;enerator ; ,
f [W'weferlevektrip lo 'irriot usedthe i tua ' f ant' ind acci'de'nt analyses tiut is j sinc 1'uddd' in Ta' bled 2,2 1 toxinsur'
/;<tripfs', 'gs' d f.he"
'enh'an e ofdn' the#, r,arlio6al refia6111gahaci[l.f'*f of the of<tkReactor' 'specified
/
L S tem.' tr,ip M ani to the'4te'am Ge'ca [' Prot'ectL65-tow $f.ri. F6'ed'/s / this tii actIvatedA en't lste' T
' 1% wa xceids'.the feedwatev,floy'by grea ,
tharr'or
'equar,tof( T/lx' 08)/,1b ' Org.The Steam Generator Lcw Water level pper' tion 7 of s' ivat i'witer/,Tever d s elowf(25) percent, av' /
.ndr' w,ca. ew: ttrry[e',fnst'rument. ,fthe's t ho/theftri dicaf, al)$wan,eIt precpvalues'includ(sufficie[fiti 6de spuri trips bu't wflMjp%in tia i a,r ac ces' ,of 11o'rmal"operatfng,y'41 / des /ttrtp' befdre'the<
Therefore, srt'eaVgener the rdqiiir,ed capsci 5 n stadt'ing' ti_mV gt(irements:o,f'the a iary feeblater pumpd'areGredged' t regultinga ,t ijtiansiedt on the Aeagtor Codlant
'6ystem a'nd stdam, generators is'ainimi d/
Undervoltaae and Underfrecuency - Reactor Coolant Pumo Busses - The Undervoltage and Underfrequency Reactor Coolant Pump Bus trips provide reactor core protection against DNB as a result of completa loss of forced coolant flow. The specified setpoints assure a reactor trip signal is generated before the low flow trip setpoint is reached. Time delays are incorporated in the underfraquency and undervoltage trips to prevent spurious reactor trips from momentary electrical power transients, For undervoltage, W-STS B 2-7 SEP 151981
- - -- - - - - ~~
LIMITING SAFETY SYSTEM SETTINGS
/. 9 BASES -
Undervoltage and Underfrecuency - Reactor Coolant Puso Busses (Continued) the delay is set so that the time required for a signal to reach the reactor trip breakers following the simultaneous trip qf, two or more reactor coolant pump bus circuit breakers shall not exceed (1.E) seconds. For underfrequency, the delay is set so that the time required for a signal to reach the reactor trip breakeys after the underfrequency trip setpoint is reached shall not
- c. c' exceedi0.9) seconds. On decreasing power the Undervoltage and Underfrequency Reactor Coolant Pump Bus trips are automatically blocked by P-7 (a power level of approximately -1g percent of RATE 4 THERMAL POWER with a turbine impulse ,
chamber pressure at approximately 3# percent of full power equivalent); and on ) increasing power, reinstated automatically by P-7. , i Turbine Trio
,,7 A Turbine Trip initiates a reactor trip. On decreasing power the turoine trip is automatically blocked by P-9) (a power level of.approximately & percent g of RATED THERMAL POWER with a turbine impulse chamber at approximately W per-cent of full power equivalent); and on increasing power, reinstated aut matically by P-3.
Safety Injection Inout from ESF O if a reactor trip has not already been generated by the reactor protective instrumentation, the ESF automatic actuation logic channels will initiate a reactor trip upon any signal which initiates a safety injection. The ESF instrumentation channels which initiate a safety injection signal are shown in Table 3.3-3.
/ / i n Reactor Coolant Pumo BredkIn-Pos[t onNice /A1
,/ /' The Rea r Cool tP ich provide reacto core protection,against DN kar ition T areanicipatoryJrips The open/close
/ trips assure a rea r trip signal is generatedTbefore thi low flo/'ppsitfon/
t wtrip'/ .
. .setooint is re had. No credit was taken in'the/ accident analyses for operation ,
of these tri ./Their functional capabilityat' the open/close. position settings / ' f'u System.is AboverequiredP-7/to, enhance (a power levelthe overall reliability of,approximately of theqReactor a percent of RATED Protection g THERMAL POWER or/a turbine impulse chamber p'ressure at approximately 16 percent of / full power equivalent) an automati'c reactor trip will occur if more than one,' reactogcoolantpumpbreaker./isopened.. Above'P-8 (a power,. level of approx-Dimately Je percent,'of RATER / THERMAL, POWER) an automatic reactor trip will / foccur if ,bne reactor coolant, pump' breaker is' opened. OrVdecreasin'gpower'
'between P' -
8 and Pf/ an automati'c reactor tirip will occui if/more <than one reactor coolant pump breakef'is opened and% low P-7 the trip' fuitctic.yis automatically blocked. / / v c ' y t/ - PSTS S 2-8 SEP 151981
O LIMITING SAFETY SYSTEM SETTINGS BASES Reactor Trio System Interlocks / The Reactor Trip System Interlocks perfom the following functions:
/
P- On increasing power P-6 allmvs the manual blocL of the Source Range ctor trip and de-energizing of the high vettage to the detectors. On asing power, Source Range level trips are automatically reactivat and high voltage restored.j ~ P-7 On increasing er P-7 automatically enables reactor trips on low flow in more than' bag primarf coolant loop, more thn one reactor coolant pump breaker'Op(n, reactor coolant pump bus undervoltage and
, underfrequency, turbine trip pressurizer low pressure and pressurizer high level. ,0nN;ecreasing power the above listed trips are automatically blocked.
P-8 On increasing power /P-8 automatical nables reactor trips on low i i flow in one or more primarf coolant leoissynd one or more reactor l coolant puep breakers open. On dect,tasing p r the P-8 automatically I blocks the above listed trips. P-10 On increasing power P-10 allows the manual block of'tbe Intermediate Range reactor trip and the flow setpoint Power Range t'nactor trip; and automatically blocks the Source Range reactor trip and sde-energizes th/ Source Range high voltage power. On decreasing power ths, Inter-mediate Range reactor trip and the low setpoint Power Range reactor
/ trip are automatically reactivated. Provides input to P-7. N
/
/P-13 Provides input to P-7.
/
/
'g y g, pi d & "O
- f 4' ef V '. 'a d-O
- 15 "
y-STS a 2-9
e V LIMITING SAFETY SYSTEM SETTINGS ( BASES i Un tage45 Underfrequend Revetor. CooTEit Pump Busses i -. iw / // ' Ths Undervolta 'an rfrequencydescjor Coola'nt Pump bus trips provide dactor core prat ion /against DNS as a yesult of loss of voltage.or under-prequency- ttrTo'r than' one reactor coolant pump. ,The specified set points assure vreactor tr,i'p signal. is generd'ted before/the low flow trip set point is reached. , Tima< delays are incorporated in ths underfrequency and under-voltage trips,to preventespurious rea'ctorftrips from momentary elect'rical powe'r transients. F6r undervolta'ge', the delay is set so that the time required fofas)fjnaletoreacYthereact trfp' breakers after the undervoltage trip etpoint,'i / reachef ou tw ore reactor coolan't pump bus circuit breakers
/s'ha1}/ pot ' For/under' frequency, the delay is set so that j
/,tffe/Jime /excehdA.5 se'un:$erfre/r34uipfd for a41 naldvreach qdency trip set p6 int is'reac) fed 'on two or more reactor coolant pump bd'ssess'hallnotexceed0,6' seconds.[/ /,e n ,
sty I'nfection Inoutefroo<ESF
/
,sy /
[// - .If Vrsactor'tr.i as not already n genpesde'd by the 4eactor protective fr>strumentation, ph r/satitor trip upo,the n,an ESFs'Ignalautomatic wh actuation,Iogic' nfection. chancel's,,,Tfits will init.ial.e trip is , a'4.' .-.' ] provided' to pro he corej'n,icf. initiates the/evenf of a .L0 a safet'
. The ESF chapnels6ffich f ate a (51fety 16fe6 tion signa are show' dan)nttrumeritaticy Table'3'.3-3r Reactor Trio System Interlocks The Reactor Trip System Interlocks perform the following functions on increasing power:
P-6 Enables the manual block of the source range reactor trip (i.e. , prevents premature block of source range trip). P-7 Defeats the automatic block of reactor trip on: Low flow in more P-13 than one primary coolant loop, reactor coolant pump undervoltage and underfrequency, pressurizer low pressure, and pressurizer high t level. 1 P-8 Defeats the automatic block of reactor trip on turbine trip and low RCS coolant flow in a single loop. P-10 Enables the manual block of reactor trip on power range (Iow setpoint), intermediate range, as a backup block for source range, and inter-mediate range rod stops (i.e. , prevents premature block of the noted functions). p On decreasing power the opposite function is performed at reset setpoints. , :: ix ,) > The interlock setpoints are listed in Table 2.2-1. ' McGUIRE - UNIT 1 B 2-4 '1 uhr7 JUN I81
O SECTIONS 3.0 AND 4.0 LIMITING CONDITIONS FOR OPERATION i AND SURVEILLANCE REQUIREMENTS O t O
-- ,- ,,-, , --,,--,,,n, --
// '
/ /
3/4 LIMLT NG CONDIT!CNS FDR OPERATIOCAND SdVEIL
/ /,
CE OU .ENTS
/
3/4 APPL [CABR[TY // ITINbCCM TION FOR RATI / / '/ 34 0 Compliance i th ,,t Lim ti Con ti ThOpef o cor,di he
<su eeding spe ications ,is rs ufre cur the 0 L
~
ther' nditi'ons s cified tiherei exc . t upon,fa,0PER il e om th ng Cendition orpperation, ea oci ed ACTION r u em sh met 3 .2 oncom;Uiance w a ec cati hall ex s*s e[t qui ts of
,the miting'Condi,ti fo Ope tion jn'd assoc 14tV TIgN , e are
/n met iithin t., , spec f ed .ime datervaj s'. ,
peraJ. ion is re red rio to exp'iration o e Lim speci M
) on for t i ., , fiterval s , y com etion of fie ION equi .ments ts j _quirft [ -
'/ .0b Whe a Li.itin Con ' -f on for'Op on not m j,
#[ceptaso in'tne a oci ed AC ON eg'uireme t's , n' one houry lon s i
'to place th unit a DE in ch .' pecificatic'n./ oep apply [pfif'ited placi g it as ap li ole,(
- 1. At I s' HOT STAND w in the n . 6 wurs;
/
. At epst HOT SH O within foll ing 6 h es, and A Wast COL
/3.
Wp4recorr tive me ur HU, WH wi are cdmpleted th n the s sequen* 4 hours. perd operation u e(ICTI equires ts, the CT m* oe taken in ccor ce with the.-specifi ti s measu ed m e time of fai ure
/ limits Oper ion. E e n to these requiceme s ore ..eet stateth,d in the ie,Ad.'iiitaltingfor C sp if sti ,
, q p
/e u ess t. in a PJRATI MODE or the specifie con
- shall pot; /
co,p6f ti s f the mitin Condit n for Ope ation,ar,e Mt/ wi out r lia on, pro sio con ned i the ON requir p isi s 1 ngt p vent ass e enroug OP IONAL M00ESh.ents/ 4equired,d Thij/ ' pomply wi* ACTION equirem . Exceptic these requirements are.sfated
/in the ndivid ' soar-4 *4 r =
- h sI 3. 0. 5 When a system, subsystem, train, component or device is determined to [
! 2n~ h ' I be inoperable solely because its emergency power source is inoperable, or l
( ,
/r j solely because its normal power source is inoperable, it may be considered OPERABLE for the purpose of satisfying the requirements of its applicable i
l [g( Limiting Condition for Operation, provided: (1) its corresponding normal or l 13p/ -/, C emergency power sourca is OPERA 8LE; and (2) all of its redundant system (s), subsystem (s), train (s), component (s) and device (s) are OPERA 8LE, or ifkewise ' ( satisfy the requirements of this specification. Unless both conditions (1) ' ( and (2) are satisfied, within 2 hours action shall be initiated to place the : unit in a MODE in which the applicable Limiting Condition for Operation does !
\ not apply by placing it as applicable in:
- 1. At least HOT STANDBY within the next 5 hours, k
- 2. At least HOT SHUTD0hN within the following 6 hours, and i
- 3. At least COLD SHUTOOWN within the subsequent 24 hours.
~
l j This specification is not applicable in MODES S or 6. ; i ^
/'
McGUIRE - UNIT 1 OvZr 2-fff4-cW .
[ 3 ,s.v t- -G, M
?/4 C-/
f~% wey f en -
\
i l, , j , 3.0./ Limiting Conditions for Operation including the associated ACTION ,
-requirements shall apply to each unit individually unless otherwise indicated as follows:
j a. Whenever the Limiting Condition for Operation refers to systems or components which are shared for both units, the ACTION 4 requirements will apply to both units simultaneously. This will j be indicated in the ACTION section. 4 -
- b. Whenever the Limiting Condition for Operation applies to only one unit, this will be identified by th -- Ja, "" i
- 1 (;r 2)
+
- --1'""' in the MT"' ec ti- - ' st "- E s ti- f ;h; ---- "~
Ar%Ec.taZ4Z ry .rmeticor .
- c. Whenever certain portions of a specification contain operating parameters, setpoints etc., which are different for each unit, i this will be identified in parentheses or footnotes. (For i example, "... flow rate of 54,000 cfm (Unit 1) or 43,000 cfm (Unit 2)...").
i - t L t i O ) t r 4 i d I. t ) c 1 4 i l I I I l.
- Mgm-+ +e 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY
, LIMITING CONDITION FOR OPERATION i 3.0.1 Compliance with the Limiting Conditions for Operation contained in the succeeding Specifications is required during the OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet the Limiting Conditions for Operation, the associated ACTION requirements shall be met.
3.0.2 Noncompliance with a Specification shall exist when tne requirements of the Limiting Condition for Operation and associated ACTION requirements are not met within the specified time intervals. If the Limiting Condition for Operation is restored prior to expiration of the specified time intervals, C0mpletion of the Action requirements is not required. 3.0.3 When a Limiting Condition for Operation is not met, except as provided in the associated ACTION requirements, within one hour action shall be initiated to place the unit in a MODE in which the Specification does not apply by placing it, as applicable, in:
- 1. At least HOT STf.N08Y within the next 6 hours,
- 2. At least HOT SHUTUOWN within the folicwing 6 hours, and
- 3. At least COLD SHUTDOWN within the subsequent 24 hours.
Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accordance with the :pecified time limits as measured from the time of failure to meet the Limiting Condition for Operation. Exceptions to these requirements are stated in the individual Speci fications. This Specification is not applicable in MODES 5 or 6. 3.0.4 Entry into an OPERATIONAL MODE or other specified condition shal? not be made unless the conditions for the Limiting Condition for Operation are set-l without reliance on provisions contained in the ACTION requirements. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements. Exceptions to these requirements are ! stated in the individual Specifications, yf ,
/ru x p, ;n > n' Nf'5
~ ~
- 7 c &
l l ~. O W-STS 3/4 0-1 JUL 2 71981 1
APPLICABILITY SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement. 4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with:
- a. A maximum allowable extension not to exceed 25% of the surveillance interval, but
- b. The comoined time interval for any 3 consecutive surveillance intervals shall net exceed 3.25 times the specified surveillance interval.
4.0.3 Failure to perform a Surveillance Requirement within the specified time interval shall constitute a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation. Exceptions to these requirements are stated in the individual Specifications. Surveillance Requirements do not have to be performed on inoperable equipment. 4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the stated surveillance interval or as otherwise specified. 4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, and 3 components shall be applicable as follows:
- a. Inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).
i 1 9' PSTS 3/4 0-2 JUL 2 31980 1 1
O APPLICABILITY SURVEILLANCE REQUIREMENTS (Continued) 4.0.5 (Continued)
- b. Surieillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:
ASME Boiler and Pressure Vessel Required frecuencies for Code and applicable Addenda performing inservice termino 1cgy for' inservice inspection and testing insoection ano testing activities activities Weekly At least once per 7 days Montniy At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 275 days Yearly or annually At least once per 366 days
- c. The provisions of Specification 4.0.2 are applicable to the anove required frequencies for performing inservice inspection and testing activities.
- d. Performance of the above inservice insoection and testing activities I shall be in addition to otner specified Surveillance Requirements.
- e. Nothing in the ASME Boiler and Pressure Vessal Code shall be construed to supersede the requirements of any Technical Specification.
O PSTS 3/4 0-3 .NOV 2 61580
O v 3/4.1 REACTIVITY CONTROL 5,YSTEMS 3/4.1.1 BORATION CONTROL SHUTOOWN MARGIN - T,y >200*F LIMITING CONDITION FOR OPERATION 3.1.1.1 The SHUTDOWN MARGIN shall be greater than or equal to (1.6%) delta k/k for (a) loop operation.
+ .
APPLICABILITY: MODES 1, 2", 3, and 4. ACTION: With the SHUTCOWN MARGIN less than (1.6%) delta k/k, imeciately initiata anc continue boration at greatar than or equal to 7# _ gpm of a solution containing greater than or equal to ~/// ppm boron or equivalent until the requirec
~
SHUTDOWN MARGIN is restored. i SURVEILLANCE REQUIREMENTS 4.1.1.1.1 The SHUTCOWN MARGIN shall be determined to be greater than or equal to (1.6%) delta k/k:
- a. Within one hour after detection of an inoperable control rod (s) and at least once per 12 hours thereafter while the rod (s) is inoperable.
If the inoperable control rod is immovable or untrippable. the above required SHUTDCWN MARGIN shall be verified acceptable with an increased allowance for the withdrawn wortn of the immovable or untrippaole control rod (s).
- b. When in MODE 1 or MODE 2 with X,ff greater than or equal to 1.0 at least once per 12 hours by verifying that control bank withorawal is within the limits of Specification 3.1.3.6.
- c. When in M00E 2 with X,ff less than 1.0, within 4 hours prior'to achieving reactor criticality by verifying that the predicted critical control rod position is within the limits of Spacification 3.1.3.6.
- d. Prior to initial operation above 5% RATED THCRMAL POWER after each fuel loading, by consideration of the factors of e below, with the control banks at the maximum insertion limit of Specification 3.1.3.6.
*See Special Test Exception 3.10.1.
)f-STS 3/4 1-1 NOV 2 01980
i
\
REACTIVITY CONTROL SYSTEMS SURVEILLANCE REOUIREMENTS (Continued)
- e. When in MODES 3 or 4, at least once per 24 hours by consideration of the following factors:
- 1. Reactor coolant system baron concentration,
- 2. Control rod position,
- 3. Reactor coolant system average tamperature, 4 Fuel burnup based on gross thermal energy generation,
- 5. Xenon concentration, anc
- 6. Samarium concentration.
4.1.1.1.2 The overall core reactivity balance shall be compared to predicted values to demonstrate agreement within : 1%, delta k/k at least once per 31 Effective Full Power Days (EFPD). This comparison shall consider at least those factors stated in Specification (4.1.1.1.1.e), .2,ove. The predicted Peactivity values shall be adjusted (normalized) to correspond to the actual core conditions prior to exceeding a fuel curnup of 60 Effective Full Power Days after each fuel loading. 1 l 1 OCT J 575 W-STS 3/4 1-2
) ~
REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN - T,y,5,200*F LIMITING CONDITION FOR OPERATION , 3.1.1.2 The SHUTC0%N MARGIN shall be greater than or equal to 1.0*. delta k/ 4. APPLICA8ILITY: MODE 5. ACTION: With the SHUTDOWN MARGIN less than 1.0% delta k/k, immediataly initiate and continue boration at greater than or equal to W gpm of a solution containing greater than or equal to ppm boren or equivalent until the requireo SHUTDOWN MARGIN is restored. 7c c r SURVEILLANCE REOUIREMENTS 4.1.1.2 The SHUTCOWN MARGIN shall be determinec to be greater than or equal to 1.0*.' delta k/k:
- a. Within one hour after detection of an inoperable control rod (s) and at least once per 12 hours thereafter while the rod (s) is inoperable.
If the inoperable control rod is immovaole or untrippable, the SHUTDOWN MARGIN shall be verified acceptable with an increased allowance for the withdrawn worth of the immovable er untrippable control rod (s). I
- b. At least once per 24 hours by consideration of the fo11cwing factors:
l 1. Reactor coolant system boron concentration, l
- 2. Control rod position,
- 3. Reactor coolant system average temperature, 4 Fuel burnup based on gross thermal energy genaration,
- 5. Xenon concentration, and
- 6. Samarium concentration.
O l PSTS 3/4 1-3 NOV 2 0 fo80
l REACTIVITY CONTROL SYSTEMS . MODERATOR TEMPERATURE COEFFICIENT l LIMITING CONDITION FOR OPERATION 3.1.1.3 The moderator temperature coefficient (MTC) shall be:
- a. Less positive than (0) delta k/k/*E for the all rods withdrawn, beginning of cycle life (BOL), hot zero THERMAL POWER condition.
M/ 4
- b. Less negative than -(+1) x 10 delta k/k/*F for the all rods withdrawn, end of cycle life (EOL), RATED THERMAL POWER condition.
APPLICABILITY: Specification 3.1.1.3.a - MODES 1 ano 2* only#. Specificatior 3.1.1.3.b - MODES 1, 2, and 3 only#. ACTION:
- a. With the MTC more positive than the limit of 3.1.1.3.a above, opera-tion in MODES 1 and 2 may proceed provided:
- 1. Control rod withdrawal limits are established and maintained sufficient to restore the MTC to less positive than 0 delta k/k/*F within 24 hours or be in HOT STAND 8Y within the next 6 hours. These withdrawal limits shall be in addition to the insertion limits of Specification 3.1.3.6.
- 2. The control rods are maintained within the withdrawal limits established above until a subsequent calculation verifies that the MTC has been restored to within its limit for the all rods withdrawn condition.
- 3. In lieu of any other report required by Specification 6.9.1, a Special Report is prepared and submitted to the Commission pursuant to Specification 6.9.2 within 10 days, describing the value of the measured MTC, the interim control red withdrawal limits, and the predicted average core burnup necessary for restoring the positive MTC to within its ifmit for the all rods withdrawn condition.
- b. 'I the MTC more negative than the limit of 3.1.1.3.b above, be in 1 A SHUTDOWN within 12' hours. !
l l
"Wita X,7f greater than or equal to 1.0. #See Special Test Exception 3.10.3. i O
W-STS 3/4 1-4 MAY l 5 'S80
==
O' REACTIVITY CONTROL SYSTEMS i SURVEILLANCE REQUIREMENTS 4.1.1.3 The MTC shall be detarained to be within its limits during each fuel cycle as follows: I- a. The MTC shall be measured and compared to the BOL limit of Specifi-l cation 3.1.1.3.a. above, prior to initial operation above FJ of l RATED THERMAL POWER, after each fuel laading.
- b. The MTC shal,
-3.a. -4MF) x 10 } be delta measured at rods k/k/*F (all any withdrawn, THERMAL RATEDPOWER and compared THERMAL POWER to condition) within 7 EFPD after reaching an equilibrius boron concan-tration of 300 ppa. I is more negative than Mq 1he x 10 event.$his comparison delta k/k/*F, tneindicates thebeMTC MTC shall remeasured, and compared to the EOL MTC limit of specification 3.1.1.3.b, at least once per 14 EFPD during the remainder of the fuel cycle.
O l 1 1 O tSTS 3/4 1-5 AUG 1 gyg
REACTIVITY CONTROL SYSTEMS MINIMUM TEMPERATURE FOR CRITICALITY LIMITING CONDITION FOR OPERATION 3.1.1.4 The Reactor Coolant System lowest shall be greater than or equal to (4M)'F. operating loop temperature (Tavg) APPLICABILITY: MODES 1 and 2'# . ACTION: less than
#T/ With (5M)*F, a Reactor restore Coolatit T System to withinoperating loop its limit temperature within (T"U)be in HOT 15 minutes STAND 8Y within thea ytgxt 15 minutes.
SURVEILLANCE REOUIREMENTS 4.1.1. 4 The Reactor Coolant System temperature (T**9) shall be determined to be greater than or equal to (4*T)*F: J~5/
- a. Within 15 minutes prior to achieving reactor criticality, and
- b. At least once per 30 minutes when the reactor is critical and the Reactor Coolant System T is less than (4&t)'F with the T -Tavg ref Deviation Alarm not rese D 9 f6/
FWith X greater than or equal to 1.0.
*SeeSpI$,lalTestException3.10.3.
N Y 151979 O
'f-STS 3/4 1-6 m__ _____ _ _ - _ _ _ _ _ - _ _ - .
REACTIVITY CONTROL SYSTEMS 3/4.1.2 80 RATION SYSTEMS FLOW PATH - SHUTOOWN LIMITING CONDITION FOR OPERATION 3.1.2.1 As a minimum, one of the following baron injection flow paths shall be OPERABLE and capable of being powered from an OPERABLE emergency power source. a. A flow path from ghgboric acid tanks via eit.M a boric acid transfer pump er . ,. r:f ty f;ed csanecti= :.% a cnarging pump to the Reactor Coolant System if the boric acid storage tank in Specification (3.1.2.3a) is OPE 3ABLE, or
- b. The flow path from the refueling water storage tank via a charging pump to the Reactor Coolant System if the refueling water storage tank in Specification (3.1.2.5b) is OPERABLE.
APPLICA8ILITY: MODES 5 and 6. ! ACTION: With none of the above flow paths CPERA8LE or capable of being powered from an OPERABLE emergency pcwer sourca, suspend all operations involving CORE ALTERATIONS or positive reactivity changes. SURVEILLANCE' REQUIREMENTS 4.1.2.1 At least one of the above required flow paths shall be demonstrated OPERABLE:
- a. At least once per 7 days by verifying that the temperature of the heat traced portion of the flow path is greater than or equal to (65)*F when a flow path from the boric acid tanks is used.
- b. At least once per 31 days by verifying that each valve (manual, power operated, or automatic) in the flow path that is not locked, sealed, or othe mise secured in position, is in its correct position.
t i PSTS . 3/4 1-7 JUL 2 71981 l
l REACTIVITY CONTROL SYSTEMS FLOW PATHS - OPERATING LIMITING CONDITICN FOR OPERATION 3.1.2.2 At least two of the following three baron injection flow paths shall be OPERABLE:
- a. The flow path from the boric acid tanks via a boric acid transfer pump and a charging pump to the Reactor Coolant System.
- b. Two flow paths from the refueling water storage tank via charging pumps to the Reactor Coolant System.
APPLICABILITY: MODES 1, 2, 3, and 4#. ACTION: With only one of the above required baron injection flow paths to the Reactor Coolant System OPERABLE, restore at least two boron injection flow paths to the Reactor Coolant System to OPERA 8LE status within 72 hours or be in at least HOT STAN08Y and borated to a SHUTD0hN MARGIN equivalent to at least 1% delta k/k at 200*F within the next 6 hours; restore at least two flow paths to OPERABLE statu:: within the next 7 days or be in COLD SHUTDOWN within the next 30 hours. SURVEILLANCE REOUIREMENTS 4.1.2.2 At least two of tne above required flow paths shall be demonstrated OPERA 8LE:
- a. At least once per 7 days by verifying that the temperature of the heat traced portion of the flow path frcm the boric acid tanks is greater than or equal to (65)*F when it is a required water source.
- b. At least once per 31 days by verifying that each valve (manual, power operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
l c. At least once per 18 months during shutdown by verifying that each I automatic valve in the flow path actuates to its correct position on a f L . . ;.2 D hty Injech h ( Ss ) M S& */. l d. At least once per 18 months by verifying that the flow path required by Specification 3.1.2.2.a delivers at least 30 gpm to the Reactor Coolant System. l 0nly one baron injection flow path is required to be OPERA 8LE whenever the l temperature of one or more of the RCS cold legs is less than or equal to ( M )*F. Soc W-STS 3/4 1-8 g,g ,,
.cg
REACTIVITY CONTROL SYSTEMS CHARGING PUMP - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1. 2. 3 One charging pump in the baron injection flow path required by Specification (3.1.2.1) shall be OPERABLE and capable of being powered from an OPERABLE emergency power source. APPLICABILITY: MODES 5 and 5. ACTION: With no charging pump OPERABLE or capable of being powered from an OPERABLE [ emergency power source, suspend all coerations involving CORE ALTERATIONS or positive reactivity changes.
., SURVEILLANCE REQUIREMENTS 4.1.2.3.1 The above recuired charging pump shall be demonstrated OPERABLE by verifying, that en recirculation flow, the pumo develcps a discharge pressure of greater than or equal toRV^^ psig when tested pursuant to Specification 4.0.5.
4.1.2.3.2 All charging pumos, excluding the above required OPERABLE pump, shall be demonstrated inoperable at least once per 12 hours, except when the reactor vessel head is removed, by verifying that the motor circuit breakers have been removed from their electrical power supply circuits,. er A y verr fy Inf %- Erc4*rre e f <a c h j'u"rf Aa s dan is ' /" M fr.w Me renc fee cec / ant ry s k m Jy o f h a s ?' W j st /s 6 : n ya by s w , % 4 ,r w + c re me u a c/ 4 'w PAL krh e- cp ras'rer ( 1 O
'pSTS 3/4 1-9 JUL 2 7198f
REACTIVITY CONTROL SYSTEMS l CHARGING PUMPS - OPERATING l LIMITING CONDITION FOR OPERATION l 3.1. 2. 4 At least two charging pumps shall be OPERABLE. APPLICA8ILITY: MODES 1, 2, 3 and 4#. ACTION: With only one charging pump OPERABLE, restore at least two charging pumps to OPERABLE status within 72 hours or be in at least HOT STANOBY and borated to a SHUTOOWN MARGIN equivalent to at least 1% delta k/k at 200*F within the next 6 hours; restore at least two charging pumps to OPERABLE status within the next 7 days or be in COLD SHUTOOWN within the next 30 hours. SURVEILLANCE REQUIREMENTS O 4.1.2.4.1 At least two charging pumps shall be demonstrated OPERABLE by verifying, that on recirculation flow, each pump develops a discharge pressure of greater than or equal to WTC psig when tested pursuant to Specification 4.0.5. 4.1.2.4.2. All charging pumps, except the above required OPERABLE pump, shall be demonstrated inoperable at least once per 12 hours when i the temperature of one or more of the RCS cold legs is less than or equal wo Fr5-)*F by verifying that the motor circuit breakers have been removed from their electrical power
/w"t!/'Ne An been b
supply circuits. jp/arhal f,<nl crHrR<ector e y wrifyinf f4~ dire Cre/an?'- /torpeb yc Sy'htm fof
<*'/*
ko' jg/qfg,, y 4 /a..s wlfA fewer remcn-</ frem th e- Va A e- ytre krs. A maximum of one centrifugal charging pump shall be OPERABLE whenever the temperature of one or more of the RCS cold legs is less than or equal to (2M)* F. 3co O W-STS 3/4 1-10 MAY I 5 579
1 REACTIVITY CONTROL SYSTEMS ' BORATED WATER SOURCE - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.5 As a minimum, one of the following borated water sources shall be OPERABLE:
- a. A boric acid storage system and at least one associated neat tracing system with:
- 1. A minimum contained barated water volume of 3'//r gallons, Ji cc e 1, 7t c
- 2. Setween (2^,000) and (22,000} ppm of boron, and 45*
- 3. A minimum solution temperature of (445i*F.
- b. The refueling water storage tank with:
.Q v,
- 1. A minimum contained borated water volume of gallons,
- 2. A minimum coron concentration of (2000) ppm, and
/s 7c
- 3. A minimum solution temperature of (49)*F.
APDLICA8ILITY: MODES 5 and 6. ACTION: With no borated water source OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes. l l SURVEILLANCE REQUIREMENTS l 4.1. 2. 5 The above required borated water source shall be demonstrated OPERABLE:
- a. At least once per 7 days by:
- 1. Verifying the boron concentration of the water,
- 2. Verifying the contained borated water volume, and
- 3. Verifying the boric acid storage tank solution temperature when it is the source of borated water.
- b. At least once per 24 hours by verifying the RWST temperature when it is the source of borated water and the (outside) air temperature is l 1ess than (.39)*F.
70 W-STS 3/4 1-11 NOV 2 01980
l l REACTIVITY CONTROL SYSTEMS
/
BORATED WATER SOURCES - OPERATING LIMITING CONDITION FOR OPERATION 3.1. 2. 6 As a minimum, the following borated water source (s) shall be OPERA 8LE as required by Specification 3.1.2.2: I
- a. A boric acid storage system and at least one associated heat tracing j system with: ;
l9c"'gallons, i
- 1. A minimum contained borated water volume of '
7 cco 7 7cc
- 2. Between (-2,_,000) and W,, Ae') ppm of baron, and c5
- 3. A minimum solution temperature of (M9)*F.
- b. The refueling water storage tank with: __
at Ms'gy g cc. A contained borated water volume of betr:r.
- 1. ---rand ~
gallons,
- 2. Between (200C) and (2100) ppa of boren, and 70
- 3. A minimum solution temperature of (M)*F.
APPLICABILITY: MODES 1, 2, 3 and 4. ACTION:
- a. With the boric acid storage system inoperable and being used as one of the above required borated water sources, restore the storage system to OPERA 8LE status within 72 hours or be in at least HOT STAN08Y within the next 6 hours and barated to a SHUTCOWN MARGIN equivalent to at least 1% delta k/k at 200*F; restore the boric acid storage system to OPERA 8LE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours.
- b. With the refueling water storage tank inoperable, restore the tank to OPERA 8LE status within one hour or be in at least HOT STANOBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
O
)t-STS 3/4 1-12 .M0y 2 01980
l c l REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS l 4.1.2.6 Each borated water source shall be demonstrated CPERABLE:
- a. At least once per 7 days by:
I
- 1. Verifying the boron concentration in the water,
- 2. Verifying the contained borated water voluine of the water source, anc
- 3. Verifying the boric acid storage system solution temcerature when it is the source of borated water.
- b. At least once per 24 hours by verifying the RWST temperature wnen the (outside) air temperature is less than (at)*F.
7C l l l l w-sTs 3/4 1-13 NOV 2 0 E20 1
REACTIVITY CONTROL SYSTEMS 3/4.1.3 MOVABLE CONTROL ASSEMBLIES GROUP HEIGHT LIMITING CONDITION FOR OPERATION 3.1.3.1 All full length (shutdown and control) rodsAr.d :P part-4ength-rods-which r: *n: -ted *- the-coce shall be OPERABLE and positioned within c 12 steps (indicated position) of their group step counter demand position. APPLICABILITY: MODES 1" and 2*. ACTION:
- a. With one or more full length rods inoperable due to being immovable as a result of excessive friction or mechanical interference or known to be untrippable, determine that the SHUTDOWN MARGIN require-ment of Specification 3.1.1.1 is satisfied within 1 hour and be in HOT STAND 8Y within 6 hours.
- b. With more than one full er p-! length rod inoperable or misaligned from the group stap counter demand position by more than 12 steps-(indicated position), be in HOT STAN08Y within 6 hours.
- c. With one full cr ; rt length rod trippable but inoperable due to causes other than addressed by ACTION a, above, or misaligned from its group step counter demand height by more than : 12 steps (indicated position), POWER OPERATION may continue provided that within one hour either:
- 1. The red is restored to OPERA 8LE status within the above alignment requirements, or
- 2. The rod is declared inoperable and the remainder of the rods in the group with the inoperable rod are aligned to within : 12 steps of the inoperable rod while maintaining the red sequence and insertion limits of Figures (3.1-1) and (3.1-2). The THERMAL POWER level shall be restricted pursuant to Specification (3.1.3.6) during subsequent operation, or
- 3. The rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied. POWER OPERATION may then continue provided that:
a) A reevaluation of each accident analysis of Table 3.1-1 is ) performed within 5 days; this reevaluation shall confirm that the previously analyzed results of these accidents remain valid for the duration of operation under these conditions.
'b) The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours. "See Special Test Exceptions 3.10.2 and 3.10.3.
! W-STS 3/4 1-14 =NOV 2 1997 l
._ _ _ . . . . . l l
REACTIVITY CONTROL SYSTEMS ACTION (Continued) c) A power distribution map is obtafned from the movable incere detectors and F (Z) and F' a within their limits wikhin 72 ho$s.re verified to be d) The THERMAL POWER level is reduced to less than or equal to 75% of RATED THERMAL POWER within the next hour and within the following 4 hours the high neutron flux trip setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER. SURVEILLANCE REQUI'Lm.ENTS l l 4.1.3.1.1 The position of each full e d ;:-t lengtn rod shall be determined to be within the group demand limit by verifying the individual rod positions at least once par 12 hours except during time intervals when the Rod Position Dev.ation Monitor is inoperable, then verify the group positions at least once per 4 hours. 4.1.3.1.2 Each full length rod not fully inserted-e..d each p:-t Ter.;th r~3--.
' hich h 4 ::-;.4 in the-core-shall be determined to be OPERABLE by movement of at least 10 steps in any one direction at least once per 31 days.
l l l s 3/4 1-15 MOV 2 G ! PSTS
l O TABLE 3.1-1 ACCIDENT ANALYSES REOUIRING REEVALUATION IN THE EVENT OF AN INOPERA8LE FULL OR PART LENGTH R00 Rod Cluster Control Assembly Insertion Characteristics Rod Cluster Control Assembly Misalignment Loss Of Reactor Coolant From Small Ruptured Pipes Or From Cracks In Large Pipes Which Actuates The Emergency Core Cooling' System Single Rod Cluster Control Assembly Withdrawal At Full Power Major Reactor Coolant System Pipe Ruptures (Loss Of Coolant Accident) Major Secondary System Pipe Rupture Rupture of a Control Rod Drive Mechanism Housing (Rod Cluster Control Assembly Ejection) o i I l l 9 W-STS 3/4 1-16 OCT 1 576
m wee -wes r-g-- r .r..w 4
< REACTIVITY CONTROL SYSTEMS POSITION INDICATION SYSTEMS-OPERATING LIMITING CONDITION FOR OPERATION av./
3.1. 3. 2 The shutdown,Acontrol :nd p:-t 1:ngt.'..c:::r:i rod position indication system and the demand position indication system shall be OPERABLE and capable of determining the control rod positions within : 12 steos. APPLICABILITY: MODES 1 and 2. ACTION: a'. With a maximum of one rod position indicator per bank inoperacle either:
- 1. Determine the position of the non-indicating rod (s) indirectly by the movable incore detectors at least once per 8 hours and immediately after any motion of the non-indicating red wnica exceeds 24 steps in one direction sinca the last determination of the rod's position, or 1
O 2. Reduce THERMAL POWER TO less than 50% of RATED THERMAL POWER within 8 hours.
- b. With a maximum of one demand position indicator per bank inoperable either:
- 1. Verify that all rod position indicators for the affected bank are OPERA 8LE and that the most withdrawn rod and the least withdrawn rod of the bank are within a maximum of 12 steps of each other at least once per 8 hours, or
- 2. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 8 hours.
SURVEILLANCE REQUIREMENTS 4.1.3.2 Each rod position indicator shall be determined to be OPERABLE by verifying that the demand position indication system and the rod position indication system agree within 12 steps at least once per 12 hours except during time intervals when the Rod Position Deviation Monitor is inoperable, then compare the demand position indication system and the rod position indica-tion systsa at least once per 4 hours. O ~. PSTS 3/4 1-17 JUL 151979
i REACTIVITY CONTROL SYSTEMS POSITION INDICATION SYSTEM-SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.3.3 One rod position indicator (excluding demand position indication) shall be OPERABLE and capable of determining the control rod position within 2 12 steps for each shutdown Fcontrol-c ;::: 1;n;tr rod not fully inserted. APPLICABILITY: MODES 3*#, 4*# and 5*#. ACTION: With less than the above required position indicator (s) OPERA 8LE, immediately open the esactor trip system breakers. SURVEILLANCE REOUIREMENTS 4.1.3.3 Each of the above required rod position indicator (s) shall be determined to be OPERABLE by performance of a CHANNEL FUNCTIONAL TEST at least once per 18 months. "With the reactor trip system breakers in the closed position.
- See Special Test Exception 3.10.5.
O W-STS 3/4 1-18 NOV 2 0 ISSO
REACTIVITY CONTROL SYSTEMS R00 DROP TIME LIMITING CON 0! TION FOR OPERATION 3.1. 3. 4 The individual full lengtn (shutdown and control) rod drop time from the fully witndrawn position shall be less than or equal to (2.2) seconds Jeem OY') fn ,n beginning'of decay of stationary gripper coil voltage to dashpot entry with: '
- a. T,yg greater than or. equal to (4M) F, and 5 57
,g 7 3
)
- b. All reactor. coolant pumps operating. Q ""^
APPLICA8ILITY: MODES I and 2. ACTION:
- a. With the drop time of any full length rod determined to exceed the above limit, restore the rod drop time to within the above limit prior to proceeding to MODE 1 or 2.
Ni c .
- b. With the rod drop times within limits but determined with n reactor O coolant pumps operating, operation may proceed provided THERMAL POWER is restricted top
, t' 'a tg e ai ped,'
fi Less than or equal to (76)% of RATED THERMAL POWER Ahr th;
- e!~ :::1:.-t ete- 'f e'"~ Nthenonoperating-loop ar; closed.~
SURVEILLANCE RE0VIREMENTS i 4.1.3.4 The red drop time of full length rods shall be demonstrated through measurement prior to reactor criticality: I
- a. For all rods following each removal of the reactor vessel head,
- b. For specifically affected individual rods following any maintenance on or modification to the control rod drive system wnich could affect the drop time of those specific rods, and
- c. At least once per 18 months.
i l O W-STS
~ 3/4 1-19 D1 3 73
REACTIVITY CONTROL SYSTEMS SHUT 00*wN RCD INSERTION LIMIT LIMITING CONDITION FOR OPERATION 3.1.3.5 All shutdown rods shall be fully withdrawn. APPLICA8ILITY: MODES 1* and 2"#. ACTION: With a maximum of one shutdown rod not fully withdrawn, except for surveillance testing pursuant to Specification (4.1.3.1.2), within 1 hour either:
- a. Fully withdraw the rod, or
- b. Declare the red to be inoperable and apply Saecification (3.1.3.1).
O SURVEILLANCE REQUIREMENTS 4.1.3.5 Each shutdown rod shall be determined to be fully withdrawn:
- a. Within 15 minutes prior to withdrawal of any rods in control banks A, B, C or 0 during an approach to reactor criticality, and
- b. At least once per 12 hours thereafter.
l "See Special Test Exceptions 3.10.2 and 3.10.3. l
#With K,ff greater than or equal to 1.0.
t l l O W-STS 3/4 1-20 'NOV 2 0 ,"cSO
O REACTIVITY CONTROL SYSTEMS l l CONTROL ROO INSERTION LIMITS LIMITING CONDITION FOR OPERATION 3.1.3.6 The control banks shall be limited in physical insertion as shown in Figures (3.1-1) and (3.1-2). APPLICA8ILITY: MODES 1* and 2*#. ACTION: With the control banks inserted beyond the above insertion limits, excapt for surveillance testing pursuant to Specification (4.1.3.1.2), either:
- a. Restore the control banks to within the limits within 2 hours, or
- b. Reduce THERMAL POWER within 2 hours to less than or equal to that f.-action of RATED THERMAL POWER which is allowed by the groue position using the above figures, or
- c. Se in at least HOT STANDBY within 6 hours.
SURVEILLANCE REQUIREMENTS 4.1.3.6 The position of each control bank shall be determined to be within the insertion limits at least once per 12 hours except during time intervals when the Rod Insertion Limit Monitor is inoperable, then verify the individual rod positions at least once per 4 hours.
*See Special Test Exceptions 3.10.2 and 3.10.3.
#With K,ff greater than or equal to 1.0.
l O W-STS 3/4 1-21 NOV 2 01550
O (FULLY WITHDRAWN) 228' :
' i i /i I l i .i.l I I l .
i i' ! l l l l ' 200 i
, i l i
l _.p_ __.
. _1.. i _' _. q __.
t ! - I !
- BANK C '
2 ! : - ' I ! /! 3 l -
. [-Y i N I [
h o 150 --i i - t' l r-- - - -
'=- l
! 'j/
f . -N-- ,
~
r
=. THIS FIGURE FOR ILLUSTRATICN ONLY I.iJ j CO NOT USE FOR CPERATICN s .
[ f l
~
- [ S~
5 ( : - e C i ! ! ' , BANKD i c 100 I c 1 i ; , a . m._ . c j i !
/.i / i i i i i ! ! . i i ! .
--.__y.-__, , , -- .. ;-. ,
r . . i l 50 -
!-j -
i i
- - l- -- - r - - '
I . [ l. .
- t. l .__..a._.
i i. s. l ! - ! ! !
! i
/ I I i i I . i
, /! i i ~~ i . r T-~~T 0
- f. (,+
,c I 0.0 0.2 0.4 0.6 0.8 g
gk,1 (FULLY INSERTED) g FRACTION OF RATED THERMAL POWER
/ FIGURE 3.11 i
ROD GROUP INSERTION LIMITS VERSUS THERMAL POWER ! THREE LOOP OPERATION O l g-sTs 3/4 1 22 007 1 to!75 1 l
~
i s' g i \ Nj r . ..s f) v (f ully Withdrcur-) (. a.228 (0.78.228) 228 _
- r
/
/
200 '
/ /-- --- . _ - _ _
,- BANKB f i l j': --l f0.0,16.ii -
2[_ 'I'0- [64j _ 2 ,go _/, - . - A O 2 un __ j
- '/ ._ :
'/
9 , h,,, ,#~ --
~
l , BANK C j^ l
<^s\ #
en
-"/ '/ -
*^:~,
Q,si x / '.-"- z 100
/
c3 ' O / ,C BANKD ~-
~
f -- f
,-' /
k0.0, SOP ,[
/ .-
/. . _ _
/ ~
** ** *' ~
0 - 0 0.2 0.4 0.6 0,8 1,o fn FR ACTION OF RATED THERMAL POWER FIGURE 3.1-1. ROD BANK INSERTION LIMITS VERSUS TH ERMAL POWER FOUR LOOP OPERATION (e)
$ v' ki &
McGUIRE - UNIT 1 3/4 1-22 VNW A
l FIGURE 3.1-2 left blank pending NRC approval of three loop cperation. i l l i l l l l 3 McGUIRE - UNIT 1 3/4 1-23 UNIT 2
1 1 i J (Fully withdrawn) 228 _ _;.._.n :c _- ,- j ._#_. ... _.; . 2 - _ .-.. . _ . . ..-_s. ..-....- - s e . .- . . _....t_, 1
. - _ _ _ _ , f _ . _ _ . _ . . . _ ..... .
_ _._..... . . , _._ . . _ . _ , . _ . .__. ~_.._ .. . .. . . _ . .. _=._-+_ - - _ _ _.s_ ._4_ ..._._. 2C0 =
, , : _ . + . . . . _ . , __ _ _ . _ . . .
.. ...,._.. ... . . r _.
,- . _ _ . . . . . .. . _ . _ . _ ..i____=_=.+.._s
__f__.,_._____r__.- ,f -,.
+ __ . _ .. . -_
_ _. .._ .__3 .__.__ .
._i_....
z _ _ _ _
;- ...)
o_ , _
-__p._..= -_
_f.. x m
=f y . ,-
1
; : ;" ~ ~ _ . . _ _
3 , - - ,. _ _.. _ " H - _ . , ; - ~, ,; _ D _ THis FIGURE FOR ILLUSTRATICN ONLY '/- - - - * - - - a,, - DO NOT USE FOR OPERATION - -
- D _-_
. _'.'m._. _~~~ _
o __ _.i _ . , f . _ . . e 100 _ _ _ _ . a
, r l
t c .-- .- a : , o : _. .. C .:-
; _ _ =._
j ,
=
I BANK D =-
- + .
50 _ --
- w . ____.,_.-_. _...
- .-- >_ : __-a ._ ....
.. .+.
___t._...._. ._-.._-
.p.___.__.._4..._.__
4.._..
=
.c,, _ __ ; ._. __.3.
=_.p_T,._._,_._...... . . _ ... .. .__ .. ._. . . . .
..,c.
. _. w_ -.._. . ..__. _.._.__. _
_-+. .+ . _ . . e, ,, .- _ _ .._ _ .._ .. .-. . - .- . . -. .- _- .-_" .-. -
. . w_.. _ .. ,_. . _. ... ....
- - + - -
----'--r---* -
O - - - - - - - - - r- -- O.0 0.2 0.4 0.6 0.8 1.0 (Fully inserted) FRACTION OF RATED THERMAL POWER Figure 3.12 ROD GROUP INSERTION LIMITS VERSUS THERMAL g POWER FOUR LOOP OPERATION y-STS 3/4 1-23 007 1 1973
i p Q L xN REACTIVITY CONTROL SYSTEMS
/y
- A ,
PART LENGTH R00 INSERTION LIMITS (OPTIONAL) l
\
LIMITING CONDITION FOR OPERATION /
\, '
3.1.3.7 The part length control rod bank shall be: N
- a. Limited in physical insertion as shown on Figure (3.1-3), and N
- b. Limited from' covering any axial segment of the fuel .aIsemblies for a period in excess of (18) out of any 30 Equivalent Full Power Days.
APPLICABILITY: MODES i" and 2*. ACTION:
- a. With the part length control rod bank inserted beyond the insertien limit of Figure (3.1-3), eithe :
~
- 1. Withdraw the part lengthj control rod bank to within the limit within 2 hours, or
- 2. Reduce THERMAL POWE within 2 hours to less than or equal to that fraction of RATED THERMAL ~ POWER which is allowed by the bank position us hg the above figure, or
- 3. Be in at leas HOT STAND 8Y within 6 hours.
b.
/
With the neutr9n absorber section of the part length control rod bank covering /any axial segment of the fuel assemblies for a period exceeding out of any 30 consecutive EFP0 period, either:
- 1. Reposition the part length control rod group to satisfy the a ove limit within 2 hours, or
- 2. Be in at least HOT STAND 8Y within the next 6 hours.
\
SURVEILLA CE REQUIREMENTS 4.1 3.7 The position of the part length control rod bank shall be determined a least once per 12 hours. I l
"See Special Test Exceptions 3.10.2 and 3.10.3.
I --J-.-,, g Cl W-STS 3/4 1-24 NOV 2 01080 l
REAC11VITY CONTROL SYSTEMS l&./.sz f( A -
&I N
PdRT LENGTH ROD INSERTION LIMITS (if required by ON8 considerations)
'N LIMITING CONDITION FOR OPERATION
\
3.1.3.7 Allhurtlengthrodsshallbefullywithdrawn. l \ . APPLICA8ILITY: ACOES 1* and 2". '
/
ACTION: \ s y / With a maximum of one part length rod not ful,1y withdrawn, within 1 hour either: ' s
- a. Fully withdraw th roc, or
- b. Se in at least h07 STANOBY within the next 6 hours.
x
,/
/ \ \
Os SURVEILLANCE REQUIREMENTS \
\
4.1.3.7 Each part length rod shall be determined to be fully withdrawn by:
- a. Verifying the position of the part le\ngth rod prior to increasing THERMAL POWER above 5% of RATED THERMAL POWER, and
- b. , Verifying, at least once per 31 days, that electric power has been
( ,' disconnected from its drive mechanism by physical removal of a ! / breaker from the circuit. 'N l /
\
\.
\
\
^ See Special Test Exceptions 3.10.2. and 3.10.3. \
D e /e ,'Ltc
./
O PSTS 3/4 1-25 N OV 2 0 1c80
O
^
/; o a
PART LENGTH RCD GRCUP INSERTION LIMIT VERSUS THERMAL POWER FIGURE 3.1-3
/
i i O l l l O
'f-STS 3/4 1-26
- - - - - - . . , . ~. - .-.
3/4.2 POWER OISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX OIFFERENCE LIMITING CONDITION FOR OPERATION 3.2.1 The indicated AXIAL FLUX DIFFERENCE (AFD) shall be maintained within the following target band (flux difference units) about the target flux difference:
- a. :
5% for core average accumulated burnup of less than or equal to 3000 MWD /MTU.
- b. + 3%, -12*.' for core average accumulated burnup of greater tnan 2000 MhD/MTU.
r - APPLICABILITY: MODE 1 above 50% of , RATED THERM'AL P0hER"., ACTION: '
/,.
/,
a. O With the indicated AXIAL FLUX DIFFERENCE outside of the' above 1 reouired target band accut the target flux difference and with THERMAL POSER: / 1Y
/
Acove 90% of RATED THERMAL POWER, within 15 minutes either: / a) Restore the indicated AFD to within the acove required f.,gt,ia N target band limits, or pa b) r# #' Reduce THERMAL POWER to less than 90% of RATED THERMAL POWER. 2." Setween 50% and 90% of RATED THERMAL POWER:
- a) POWER OPERATION may continue provided:
f(/ l
#).
1 The indicated AFD has not been outside he above required target band for more than I hour penalty - deviation cumulative during the previous 24 nours,/ ' and
/ / ~
- 2) ,The indicated.AFD is within the' limits shown on Qqure 3.2-1. Otherwise, reduce THERMAL. POWER to less than 50% of RATED / THERMAL POWER within 30 minutes-and reddce the Powerf Rande Neutry/n Flux-High Trip f Setpoints to less ttran'or equal Lto'55% of RATED ~
/
THERMAL POWER with[n' the next 4 hours.
"See Soecial rest Exception 3.10.2.
McGUIRE - UNIT 1 3/4 2-1
- t/Nrt" A
. . - - ~ - - \
3/4.2 PCWER OISTRISUT!0N LIMITS 3/4.2.1 AXIAL FLUX OIF ERENCE L:MITING CONDITION FOR CPERATION
; p cueghX 0 7 ~. d hal)-c(m , aux
[arge/%"
. t band L (ficx)A1.
.er ce u ' .s) a out tme' target pata}hed,<ffaja eifferencal y APPLICABILITY: MCOE 1 above 50% of RATED THERMAL PCWER". .
ACTION:
- a. WitntheinoicatedAXIALFLUXOIFFERENCEoutsideoftne.ahypartarget band about the target flux differsnce and with THERMAL ?CWER:
Above 90% of RATED THERMAL PCWER, within 15 minutes either: 1. a) Restore the incicatad AFD to witnin the target band ifmits, or b) Recuce THERMAL PCWER to less than 90% of RATED THERMAL PCWER.
- 2. Between 50% and 90% of RATED THERMAL POWER:
a) POWER OPERAT!CN may continue provided:
- 1) The indicatec AFD nas not been outside of ne eMNr, r+ 4#d ~
target band for more than 1 hour cenalty deviation cumulative during the previous 24 hours, anc
- 2) TheindicatecA.Ws_within:nelimitssnownonk Ficure fl. 2-1). __]0thenvi se, reduce THERNAL PCwER to F less than 50% of RATED THERMAL POWER within 30 minutes I and reduce the Power Range Neutron Flux-Hign Tric Setpoints to less than or equal to 55% of RATED THERMAL PCWER witnin the next 4 hours.
b) Surveillance testing of the Power Range Neutron Flux Channels may be performed pursuant to Soecification (4.3.1.1) provided the indicatec AFD is maintained within the Ifmits of Figure 3.2-1. A total of 16 hours operation may be accumulated with the AFD outsice of tne target band during this testing without cenalty deviation.
- b. THERMAL POWER shall not be increased above 90% of RATED THERMAL POWER unless the indicated AFD is within the sesis target band anc ACTION a.2.a) 1), above has been satisfied. N f- ^'/
1 l "See Special Test Exception 3.10.2. l l PSTS 3/4 2-1 NOV o 0 '550
1 POWER OISTRISUTION LIMITS Ol j I l ACTION,(Continued)
- c. THERMAL POWER shall not be increased above 50% of RATED THERMAL I POWER unless the indicated AFD has not been outside of the sisi#r !
ny., tad target band for more than i hour penalty deviation cumulative duaing
~
l t.1e previous 24 hours. Power increases above 50% of RATED THER%. POWER do not require being within the target band provided the accumulative penalty deviation is not violated. l SURVEILLANCE RECUIREMENTS 4.2.1.1 The indicr.ted AXIAL FLUX DIFFERENCE shall be determined to be within . its limits during POWER OPERATION above 15% of RATED THERMAL POWER by:
- a. Monitoring the indicated AFD for eacn OPERABLE excore channel:
- 1. At least once per 7 days when the AFD Monitor Alarm is OPERABLE, and
- 2. At least once per hour for the first 24 hours after restoring the AFD Monitor Alarm to OPERABLE status.
- 5. Monitoring and logging the indicated AXIAL FLUX OIFFERENCE for each OPERA 8LE excor channel at least once per hour for the first 24 hours and a least once per 30 minutas thereafter, wnen the AXIAL FLUX OIFFERENCE Monitor Alarm is inoperable. The logged values of the indicated AXIAL FLUX OIFFERENCE shall be assumed to exist during the intarval preceding each logging. ,
- 4. 2.1. 2 The indicated AFD shall be considered outside of its target band wnen 2 or more OPERABLE execre channels are indicating the AFD to be outside the target band. Penalty deviation outside of the 2tSJE target band shall De accumulated on a time basis of: Yegsed
- a. One minute penalty deviation for each 1 minut'e of POWER OPERATION outside of the target band at THERMAL POWER levels equal to or acove 50% of RATED THERMAL POWER, and
- b. One-half minute penalty deviation for each 1 minute of POWER OPERATION outside of the target band at THERMAL POWER levels between 15% and 50% of RATED THERMAL POWER.
4.2.1.3 The target flux difference of each OPERABLE excore channel shall be determined by measurement at least on ce per 92 Effective Fu11 ' Power Dayser r h i. ..;M or,nt: i rL % iiy T tht r - The provisions of specification 4.0.4 are not app 1fcable. 4.2.1.4 The target flux difference shall be updated at least once per 31 Effective Full Power Days by either determining the target flux difference pursuant to 4.2.1.3 above or by if near interpolation between the most recently measured value and 0 percent at the end of the cycle life. The provisions of Specification 4.0.4 are not applicable. W-STS 3/4 2-2
.NOV 3 0 ISSO
O is 1E Oh
-Qid cE2 E555 100 UNACCEPTABLE 5(-11,90)
(11,90)EUNACCEPTABLE
~
' OPERATION ; q , OPERATION 30 .
i g ' -hCCEPTABLE1CPERAT10N".,
,. 5
( 31,'50) (31,50) 40
'. ER C.20
,} (
)!l
#/ -
lj L j 0 30 40 50 {if 50 40 -30 -20 10 0 10 20
.Y FLUX DIFFERENCE (AI) %
FIGURE 3.21 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER l !O f '* '"'" ff{ { 3/4 2-3 JUL15 g
~
l POWER DISTRIBUTION LIMITS 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR - Fg LIMITING CONDITION FOR OPERATION 3.2.2 Fq (Z) shall be limited by the following relationships: FS (Z) 1 (2.32] (X(Z)] for P > 0.5 P Fq (Z) i [(4.64)] [K(Z)] for P 5 0.5 where P = THERMAL POWER RATED THERMAL power and K(Z) is the function ootained from Figure (3.2-2) for a given core height location. APPLICABILITY: MODE 1 ACTION: With Fq (Z) exceeding its limit:
~.
, ., - . ... ;i aar oi i.n= foi i ow ing-ACTIONS;-
47 . .W Reduce THERMAL POWER at least 1% for each 1%nF (Z) exceeds the limit within 15 minutes and similiarly reduce the Power Range Neutron Flux-High Trip Setpoints within the next 4 hours; POWER OPERATION may proceed for up to a total of 72 hours; subsequent POWER OPERATION may proceed provided the Overpower delta T Trip Setpoints have been reduced at least 1% for each 1% Fg (Z) exceeds the limit. The Overpower delta T Trip setpoint reduc-tion shall be performed with the reactor in at least HOT STANDBY. X e T 'P fc'ps th
}?p&fHERMA
$YE'?/
o; o I '*
- b. Identify and correct the cause of the out of limit condition prior l
to increasing THERMAL POWER above the reduced limit required by a, above; THERMAL POWER may then be increased provided F (I) is demon-strated through incore mapping to be within its limit O W-STS 3/4 2-a SEP 151979
f POWER OISTRIBUTION LIMITS SURVEILLANCE REOUIREMENTS 4.2.2.1 The provisions of Specification 4.0.4 are not applicable. 4.2.2.2 F xy shall be evaluated to determine if F (I) is within its limit by: q ! a. Using the movable incore detectors to obtain a power distribution map at any THERMAL POWER greater than 5% of RATED THERMAL POWER.
- o. Increasing the measured F component of the power distribution map by 3% to account for manuNeturing tolerances and further increasing the value by 5% to ac::ount for measurement uncertainties.
- c. Comparing the F xy comeuted (F ) obtained in b, above to:
- 1. The F xy limits for RATED THERMAL POWER (F ) for tne acpropriate measured core planes given in e and f below, and
- 2. The relationship:
- F' xy = ( U +0.20-P)]
where F ' is the limit for fractional THERMAL POWER operation expressed as a function of F and P is the fraction of RATED THERMAL POWER at which F,y was measured.
- d. Remeasuring F xy ac::ording to the following schedule:
- 1. When F is greater than the F RTP y
limit for the appropriata measured core plane but less than the F relationship, additional . power distribution maps shall be taken a d F x c spared to F xRTP and Fxy': a) Either within 24 hours after exceeding by 20% of RATED T*lERMAL POWER or greater, the THERMAL POWER at which F was last determined, or l b) At least once per 31 EFPD, whichever occurs first. O W-STS 3/4 2-5 -
- MAY I 51975
POWER OISTRIBUTION LIMITS SURVEILLANCE RECUIREMENTS (Continued) C
- 2. When the Fxy is less than or equal to the F xRTP limit for the appropriate measured core plane, additional power distribution maps shall be taken and F ccmpared to F and F xyl at least x x once per 31 EFPO.
- e. The F R xy limits for RATED THERMAL POWER (Fx ) shall be provided for all core planes containing bank "0" control rods and all unrodded core planes in a Radial Peaking Factor Linit Report per Specifica-tion 6.9.1.10.
- f. The F limits of e, above, are not applicable in the following core planeIYregions as measured in cercent of core height from the bottom of the fuel: .
- 1. Lower core region from 0 to 15%, inclusive.
- 2. Upper core region frem 85 tn 100%, inclusive.
- 3. Grid plane regions at 17.8 t 2%, 32.1 2%, 46.4 t 2%, 60.6 2%
and 74.9 2%, inclusive (17 x 17 fuel elements).
- 4. Core plane regions within 2% of core height ( 2.88 inches) about the bank demand position of the bank "0" or part length control rods.
l
- g. With Fx exceeding xy Fy fufMORW theeffectsofFxy on Fq (Z) shall be evaluated to determine if Fq (Z) is within its limits.
4.2.2.3 When F (Z) is measured for other than F determinations, an overall measured nF (Z) 9 hall be obtained frcm a power dillribution map and increased by 3% to account for manufacturing tolerances and further increased by 5% to account for measurement uncertainty. 9
' -STS f 3/4 2-6 NOV 2 ;c5;
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l i M-STS 3/4 2-7 MM 15 g
POWER OISTRIBUTION LIMITS 3/4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALY RISE HOT CHANNEL FACTOR LIMITING CONDITION FOR OPERATION 3.2.3 The comoination of indicated Reactor Coolant System (RCS) total flow rate and R R shall be maintained within the region of allowable operation shownonFlg,ur$3.2-3for4loopoperation. Where: a. F"1H R) = 1.49 (1.0 - 0.2 (1.0 - P)] R)
- b. R 2 * (1-RSP(BU)]
p , THERMAL PCWER c* , RATED THERMAL POWER N
- d. F = Measured values of F N obtained by using the movable incore detectors to obtain a power distribution map. The measured values of Fh shall be used to calculate R since Figure 3.2-3 includes measurement uncertainties of 3.5% for flow and 4% for incore miasurement of F" , and
- e. R8P (BU) = Rod Bow Penalty as a function of region Peerage burnup as shown in Figure 3.2-4, wnere a region is defined as those assemolies witn the same loading date (reloads) or enrichment (first core).
APPLICABILITY: MODE 1. ACTION: With the combinatf or, of RCS total flow rate and R), R 2 utside the region of acceptable operation shown on Figure 3.2-3:
- a. Within 2 hours either:
- 1. Restore the combination of RCS total flow rate and R ,
7 R to within the above limits, or 2
- 2. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER and reduce the Power Range Neutron Flux - High trip setpoint to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours.
W-STS 3/4 2-8 NOV 2 01950
O POWER OISTRIBUTION LIMITS ACTION: (Continuec)
- b. Within 24 hours of initially being outside the above limits, verify through incere flux mapping and RCS total flow rate comparison that the comoination of R , R and RCS total flow rate are restored to withintheabovelimlts,2or reduce THERMAL POWER to less tnan 5% of RATED THERMAL P0kER within the next 2 hours,
- c. Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER above the reduced THERMAL POWER limit required by ACTION items a.2. and/or b. above; subsequent POWER OPERATION may proceed provided that the combination of R , R and
' indicated RCS total flow rate are cemonstratad, through }ncofe flux mapping and RCS total flow rata comparison, to be within the region of acceptable operation shown on Figure 3.2-3 prior to exceeding the following THERMAL POWER letels:
- 1. A nominal 50% of RATED THERMAL POWER,
- 2. A nominal 75% of RATED THERMAL POWER, and l 3. Within 24 hours of attaining greater than or equal to 05% of RATED THERMAL POWER.
i l SURVEILLANCE REOUIREMENTS 4.2.3.1 The provisions of Specification 4.0.4 are not appitcable. 4.2.3.2 The combination of indicated RCS total flow rate and R R shall be determinedtobewithintheregionofacceptableoperationofFlg,ure.,3.2-3:
- a. Prior to operation above 75% of RATED THERMAL POWER after each fuel loading, and
- b. At least once per 31 Effective Full Power Days.
4.2.3.3 The indicated RCS total flow rate shall be verified to be within the region of acceptable operation of Figure 3.2-3 at least once per 12 hours wnen the most recently obtained values of Ry and R2 , obtained per Specification 4.2.3.2, are assumed to exist. 4.2.3.4 The RCS total flow rate indicators shall be subjected to a CHANNEL CALIBRATION at least once per 18 months. 4.2.3.5 The RCS total flow rate shall be determined by measurement at least once per 18 months. e sTs 3f4% JUL 15 wo
9
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- ,;l: i ,
' MEASUREMENT T't I f
- c. UNCERTAINTIES .' .
-t -
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- AND 4% FOR INCORE! 4! , i I /
46 MEASUREMENT OF N
"-T' I T ,
' ' /'N F
AH AhtE INCLUDED - - s I { ACCEPTABLE IN THIS FIGURE. -j " ' OPERATION '- REGION FOR R: ONLY 44 - 3 3 g THIS' FIGURE FOR ILLUSTRATICN CNLY CONOT USE FOR OPERADON e -- N ' N ACCEPTABLE y ":
~ 42 -
OPERATION UNAC'CEPTA'BLs Q c REGION FOR R, AND R:
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% LI /I.J FIGURE 3.2 3 RCS TOTAL FLOWRATE VERSUS R - FOUR LOOPS IN OPERATION O
W-STS 3/4 2-10 NOV 15 I!T/9
O O .
'O 48 if ;
O ' MEASUREMENT UNCERTAINTIES OF ACCEf' TABLE M
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' MEASUREMENT OF FaggAREINCLUDED REGION FOR E 46 -IN Tills FIGURE, 7 Z R2ONLY k'Iq N- .
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44 3 NIEPTNLE UNACCEfrTABLE b OY. RATION GPERATION C REGONFOR REGION I- R3 &fh i - l
$ 42 I(1.016,42.0)-
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. oc REGION F0FMA R1P UNACCEI' TABLE (1.0.3R3%
38 - OPERATION - -
- , REGION 3G !
Q mo 0.00 0.02 0.04 0.00 0.00 1.00 1.02 1.04 1.06
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POWER DISTRIBUTION LIMITS 3/4.2.4 OUADRANT POWER TILT RATIO LIMITING CONDITION FOR OPERATION 3.2.4 The QUADRANT POWER TILT RATIO shall not exceed 1.02. APPLICABILITY: MODE 1 above 50% of RATED THERMAL POWER". l ACTION:
- a. With the QUADRANT POWER TILT RATIO determined to exceed 1.02 but less than or equal to 1.09:
- 1. Calculate the QUARANT ?OWER TILT RATIO at least once per hour until either:
a) The QUADRANT POWER TILT RATIO is reduced to within its limit, or b) THERMAL POWER is reduced to less than 50% of RATED THERMAL POWER.
- 2. Within 7. hours either:
a) Reduce the QUADRANT POWER TILT RATIO to within its i limit, or b) Reduce THERMAL POWER at least 3% from RATED THERMAL POWER for each 1% of indicated QUADRANT POWER TILT RATIO in excess of 1.0 and similarly reduce the Power Range Neutron Flux-High Trip Setpoints within the next 4 hours.
- 3. Verify that the QUADRANT POWER TILT RATIO is within its limit within 24 hours after exceeding the limit or reduce THERMAL
- POWER to less than 50% of RATED THERMAL POWER within the next 2 hours and reduce the Power Range Neutron Flux-High Trip
, setpoints to less than or equal to 55% of RATED THERMAL POWER l within the next 4 hours. 4 Identify and correct the cause of the out of limit concition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50% of RATED THERMAL power may proceed provided that the QUADRANT POWER TILT RATIO is verified within its limit at least i once per hour for 12 hours or until verified acceptacle at 95% or greater RATED THERMAL POWER.
"See special Test Exception 3.10.2.
O W-STS 3/4 2-12 fl0 V 2 0 iss 0
4 m
,, POWER OISTRIBUTION LIMITS ACTION: (Continued)
- b. With the QUADRANT POWER TILT RATIO detarmined to exceed 1.09 due to misalignment of either a shutdown, control or part length rod:
- 1. Calculate the QUADRANT POWER TILT RATIO at least once per hour until either:
a) The QUADRANT POWER TILT RATIO is reduced to within its limit, or b) THERMAL POWER is reduced to less than 50% of RATED THERMAL POWER.
- 2. Reduce THERMAL POWER at least 3% from RATED THERMAL POWER for each 1% of indicated QUADRANT POWER TILT RATIO in excess of 1.0, witnin 30 minutes.
l
- 3. Verify that the QUA0 RANT POWER TILT RATIO is within its limit within 2 hours after exceeding the limit or reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within tne next O 2 hours and reduce the Power Range Neutron Flux-High trip Setpoints to less than or equal to 55% of RATED THERMAL PCWER within the next 4 hours.
- 4. Identify and correct the cause of the out of limit condition prior to increasing THERMAL PCWER; subsequent POWER CPERATION aoove 50% of RATED THERMAL POWER may proceed provided that the QUADRANT POWER TILT RATIO is verified within its limit at least once per hour for 12 hours or ntil verified acceptable at 95%
or greater RATED THERMAL POWER
- c. With the QUADRANT POWER TILT RATIO determined to exceed 1.09 due to causes other than the misalignment of either a snutdown, control or part length rod:
- 1. Calculate the QUA0 RANT POWER TILT RATIO at least once per hour until either:
~
a) The QUADRANT POWER TILT RATIO is reduced to within its limit, or b) THERMAL POWER is reduced to less than 50% of RATED THERMAL
- POWER.
! O W-STS ~ 3/4 2-13 'NOV 2 0 ISSO
POWER OISTRIBUTION LIMITS ACTION: (Continued)
- 2. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 2 hours and reduce the Power Range Neutron Flux-High Trip Setpoints to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours.
- 3. Identify and correct the cause of the out of limit condition prior to increasing THERNAL POWER; subsequent POWER OPERATION above 50% of RATED THERMAL POWER may proceed provided that the QUADRANT POWER TILT RATIO is verified within its limit at least once per hour for 12 hours or until verified at 95% or greater RATED THERMAL POWER.
- d. The provisions of Specification 3.0.4 are not applicaole.
SURVEILLANCE RECUIREMENTS 4.2.4.1 The QUADRANT POWER TILT RATIO shall be determined to be within the limit above 50% of RATED THERMAL POWER by:
- a. Calculating the ratio at least once per 7 days when the alarm is OPERABLE.
- b. Calculating the ratio at least once per 12 hours during steady state operation when the alarm is inoperable.
4.2.4.2 The QUADRANT POWER TILT RATIO shall be determined to be within the limit when above 75 percent of RATED THERMAL POWER with one Power Range Channel inoperable by using the movable incore detectors to confirm that the normalized I symmetric power distribution, obtained from the 4 pairs of symmetric thimble locations, is consistent with the indicated QUADRANT POWER TILT RATIO at least once per 12 hours. l O pSTS 3/4 2-14 SEP 1'O 1980 l l
l l l O POWER DISTRIBUTION LIMITS l 3/4.2.5 ON8 PARAMETERS LIMITING CONDITION FOR OPERATION 3.2.5 The following DN8 related parameters shall be maintained within the limits shown on Table 3.2-1:
- a. Reactor Coolant System T,yg.
- b. Pressurizer Pressure.
APPLICABILITY: MODE 1. ACTION: With any of the acove parameters exceeding its limit, restore the parameter to within its limit within 2 hours or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within tne next 4 hours. ? !O SURVEILLANCE REQUIREMENTS 4.2.5 Each of the parameters of Table 3.2-1 shall be verified to be within their limits at least once per 12 hours. 4 O l PSTS 3/4 2-15 .NOV 2 01c80 l l l- ._ _
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O 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR' TRIP SYSTEM INSTRUMENTATION LIMITING CCNDITION FOR OPERATICN 3.3.1 As a minimum, the reactor trip system instrumentation channels'and interlocks of Table 3.3-1 shall be OPERABLE with RESPONSE TIMES as shown in Taole 3.3-2. APPLICA8ILITY: As shown in Taole 3.3-1. ACTION: As shown in Table 3.3-1. SURVEILLANCE RE0VIREMENT'S I 4.3.1.1 Each reactor trip system instrumentation channel and interlock and the automatic trip logic shall be demonstrated OPERABLE by the performance of the reactor trip system instrumentation survaillance requirements specified in Table 4.3-1. 6 4.3.1.2 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip function I shall be demonstrated to be within its limit at least once per 18 months. Each test shall include at least one train such that both trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function as snown in the
" Total No. of Channels" column of Table 3.3-1.
O W-STS
- 3/4 3-1 SE? t 51981
TABLE 3.3-1 'T g REACTOR TRIP SYSTEM INSTRUMENTATION HINIMUM TOTAL NO. CHANNELS CilANNELS APPLICABLE FUNCTIONAL UNIT OF CilANNELS TO TRIP OPERABLE MODES ACTION
- 1. Manual Reactor Trip 2 1 2 1 2 1 1 2 1 2 3A , 4* , 5* 13
- 2. Power Range, Neutron Flux - liigh 4 2 3 1, 2 2 Setpoint ggy y Low 4 2 3 1 ,2 2 Setpoint
- 3. Power Range, Neutron Flux 4 2 3 1, 2 2 High Positive Rate 5:' 4. Power Range, Neutron Flux, 4 2 3 1, 2 2
- liigh Negative Rate
- 5. Intermediate Range, Neutron Flux 2 1 2 1 ,2 3
- 6. Source Range, Neutron Flux gy .
A. Startup 2 1 2 2 4 B. Shutdown 2 1 2 3*, 44, 5* 13 C. Shutdown 2 0 1 3, 4, and 5 5
- 7. Overtemperature AT Mur-loop-Plant. y Four Loop Operation 4 2 3 1, 2 6 Three Loop Operation 4 1** 3 1, 2 9
/B./ 'T}}ref Loopgflant' / .-g $ '"'1hreefoop.Gperation' )3'. ' - ~). d 2/ 2 1,9 - ;7 ,- ' t Twg Loop,0peratiop ' i3 .I t
- l2 1 ;<2 " 9' u,
O O O
o o o j TAllLE 3.3-1 (Continuett)
4'
_ REACIOR 1 RIP SYSIEN INSTRUMENI A110N HINillOH !' 10lAl. NO. CllANNELS CilANNELS APPLICABLE , i FUNCTIONAL UNIT OF CilANNELS 10 IRIP OPI RAlll E H00ES ACIl0N
- 8. Overpower AT i t.. -Four-Loop-PlanL- 6, four Loop operation 4 2 3 1, 2 lhree Loop Operation 4 1** 3 1, 2 9
.II.'1Three.L'o
'2
'Th ' I'o '3- - 2: , 2 -1, 'J ,.'
I If 'ern.ioi j' ' 3'- 1** 2 1;2 S
- 9. Pressurizer Pressure-Low # t
.A; M ::p *12a' 4 2 3 1 6 j g -B. I..ee-Leep-Plant. --
3- --- 2 2 1 b Y 10. Pressurizer Pressure--lil0h y
'd A. T uu. Loop-Plant- 4 2 3 1, 2 6
! a Three-Loop Plant 3--- - 2 1, 2 - - 7,-
- 11. Pressurizer Water Level--liigh 3 2 2 1 7 )
- 12. Loss of Flow i A. Single Loop (Above P-8) 3/ loop 2/ loop in 2/ loop in 1 7, l' any oper- each oper-ating loop ating loop
- 8. Two Loops (Above P-7 and 3/ loop 2/ loop in 2/ loop 1 7 l below P-8) two oper- each oper-l ating loops ating loop l
N. e-- (JR 80
TABLE 3.3-1 (Continued) y REACTOR TRIP SYSTEM INSTRUMENIATION HINIMUH TOTAL NO. CilANNELS CllANNELS APPLICAllLE FUNCil0NAL UNIT Of CllANNELS 10 TRIP OPrilABI C H00fS ACTION 4 2/stm. gen. A
- 13. Steam Generator Water 2/sta. gen. R 2/stm. gen. 1, 2 7 Level--Low-Low in any oper- each oper-ating sim. ating stra.
gen. gen.
/ 4 / tea ne bw.'5 ta[ gen. ' 1 's tai -
~
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' / <'}efel,and / ' lev'el ;.phri.
,cideif(coin-t with level and' -
2 stin/ geed-2. f' iflow si'spatch l'strp.'/ feed- - f low ~ mismatch' in a'c)r s tm. . 'tlowTmismatch in same-sta.
, ,00 .f in sp 'stm. ' gen.:orf 2 sim.
g t' Den. , ,, gen. level and I stm/ feed- { flow mismatcl1 in samq.steain gen. '.
- 15. Undervoltage-Reactor Coolant Pumps
,15A.Q']F 9 J 1pnl/,
'ufgo'9p' 4-1/ bus 2 3
- 76f--- --
1
. 4 hree-Loop'Plartti 1/hus --- - - -- 2-- - 2 -
- 16. Underfrequency-Reactor Coolant Pennps Fo 4-1/ bus 2 3 1
.:.B.AgJh,up,
[ooplPlanty' ree'l.oop-Pl ant. . 3-1/ bus . . . _ _ _ _ . . 2 2 1 6f 7
~
un Q 17. Turbine 1 rip
- A. Low Fluid Oil Pressure 3 2 #
2 1 7
- u. 11 . Turbine Stop Valve C'osure 4 4 4 1 73
{$ O O O
O O O t 1 Allt E 3.3-1 (Continued) l If Q REACIOR 1 RIP SYS11H INSIRlMINIA110N HINIHlM 10TAL NO. CilANNElS CilANNELS APPL 1 CABLE FUNCTIONAL UNil 0F CilANNELS 10 1 RIP OPERA 0lE N00ES ACTION
- 18. Safety injection Input from ESF 2 1 2 1, 2 12
/19,',R ~
Cooj'aritNaip'replser '.' .,
*/[/p'a'ct Posit 19tffri A/ Ahoye'j // //' / -'/ -
. . -^ .
1/ breaker
,i . .'
Y /'el . i 1/ breaker 1 ' ,- '
'_1p#
t
- 8. , 'Ab6ve P 7 g id'tje^ P-8 / low // ,/ / ,2p '1/lgeakey' ! :17'
~
c 'l/lir,eakei' ,
,Al per oper .
- z. o - -
,at.ing lopp / -
< c -
- 20. Reactor Trip System Interlocks R A. Intermediate Range
- Neutron Flux, P-6 2 1 2 2,, 8 ;
- T
- 8. Low Power Reactor l Trips Block, P-7 P-10 Input 4 2 3 1 8 or P-13 Input 2 1 2 1 8 C. Power Range Neutron Flux, P-8 4 2 3 1 8
~
w the s
TABLE 3.3-1(Continue <!}
} REAC10R TRIP SYSTEM INSTRUMLHIA110N HINIMUH TOTAL NO. CilANNELS CllANNELS APPLICAULE FUNCTIONAL UNIT OF CilANNELS TO TRIP OPERABLE H0 DES ACTION D. Low Setpoint Power Range Neutron Flux, P-10 4 2 3 1, 2 8 E. Turbine Impulse Chamber Pressure, P-13 2 1 2 1 8
- 21. Reactor Trip Breakers 2 1 2 1 2 12 2 1 2 3 A, 4*, S* 13
- 22. Automatic Trip Logic 2 1 2 1, 2 12
, 2 1 2 3^, 4^, S* 13 'S Y
m CJ, 43 9 O O
TABLE 3.3-1 (Continued) TABLE NOTATION
=
With the reactor trip systes breakers in tne closed position, the control rod drive systes capable of rod withdrawal.
==
The channel (s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripoed condition. The provisions of Specification 3.0.4 are not applicable.
"Below the P-6 (Intermediate Range Neutron Flux Interlock) setpoint.
# elow B the P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.
ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channels one less than the Minimu:i Channels OPERA 8LE requirement, restore the inoceraole enannel to OPERABLE status within 48 hours or ce in HOT STANDBY within I the next 6 hours. I ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION say proceed provided the following conditions are satisfied:
- a. The inoperable channel is placed in the tripped condition within 1 hour. ,
- b. The Minimus Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 2 hours for surveillance testing of other channels per Specification 4.3.1.1.
- c. Either, THERMAL POWER is restricted to less than or equal to 75% of RATED THERMAL PCWER and the Power Range Neutron Flux trip setpoint is reduced to less than or equal to (85)% of RATED THERMAL POWER within 4 hours; or, the j QUADRANT POWER TILT RATIO is monitored at least once per i 12 hours per Specification 4.2.4.2.
O W-STS 3/4 3-7 SEP 15 IS81
TABLE 3.3-1 (Continued) ACTION STATEMENTS (Continued) ACTION 3 - With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:
- a. Below the P-6 (Intermediate Range Neutron Flux Interlock) setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6
) Setpoint.
- b. Above the P-6 (Intermediate Range Neutron Flux Interlock) setpoint but below 10 percent of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 10 percent of RATED THERMAL POWER.
ACTION 4 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement suspend all operations involving positive reactivity charges. ACTION 5 - With the numoer of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within 1 hour and at least once per 12 hours thereafter. ACTION 6 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP ad/or POWER OPERATION may proceed provided the following conditions are satisfied:
- a. The inoperable channel is placed in the tripped condition within 1 hour.
- b. The Minimum Channels OPERABLE requirement is met; however,
! the inoperable channel may be bypassed for up to 2 hours l for surveillance testing of other channels per ) Specification 4.3.1.1. 1 ACTION 7 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed until performance of the next required OPERATIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 hour. ACTION 8 - With less than the Minimum Number of Channels OPERABLE, within one hour determine by observation of the associated permissive annunciator window (s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3. O I PSTS 3/4 3-8 SEP 151981
TABLE 3.3-1 (Continued) ACTION STATEMENTS (Continued) ACTION 9 - With a channel asscciated with an operating loop inoperable, restore the inoperable channel to OPERA 8LE status within 2 hours or be in at least HOT STANOBY within the next 6 hours. One channel associated with an operating loop may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.1.1. AC 1 it ~' number.of 0PE LE Channels one 1
- 4 /AN'yt re
- th Imum Mann C l 'T d , '
tc' OP L!Niithus% in 2. re THE PCWER to / L' ' M[beit'hi tileA'Pcwer deutron I arlock) s - thedext ur Opera ' ow th s
, , /c inue' ant tvACTIO .
d_
"'i \ '4CTIC d -timber of,0PERASt.FCIanneife$e less tha ~'in'e' Minimum' I/ f' -Channels'0PERABLE r,equ[rementfoperation-ma9 contigue 'providC~
' 'the, inopersole,channer s'p'lacet 4ft"the tripped-condition
~
wyn-1 hour' _ ACTION 12 - With the number of OPERABLE channels one less than the Minimum . Channels OPERABLE requirement, be in at least HOT STAN08Y l p within 6 hours; nowever, one channel may be bypassed for uo to 2 hours for surveillance testing per Specification 4.3.1.1, 3 I ig i provided the other channel is OPERABLE. I ACTICN 13 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPEARABLE status within 48 hours or open the reactor trip breakers within the next hour. t 1 l O W-STS
- 3/4 3-9 SEP 151081
TABLE 3.3-2
'T y REACTOR 1 RIP SYSTEM INSTRUMENTATION RESPONSE TlHES FUNCTIONAL UNIT RESPONSE TIME
- 1. Manual Reactor Trip Not Applicable
- 2. Power Range, Neutron Flux $ (0.5) seconds *
- 3. Power Range, Neutron Flux, lil0h Positive Rate Not Appilcable
- 4. Power Range, Neutron Flux, liigh Negative Rate 1 (0.5) seconds *
- 5. Intermediate Range, Neutron Flux Not Applicable
- 6. Source Range, Neutron Flux Not Applicable
{
- 7. Overtemperature AT $ (4.0) seconds *
- 8. Overpower AT Not Applicable
- 9. Pressurizer Pressure--Low $ (2.0) seconds
- 10. Pressurizer Pressure--Ili0h $ (2.0), seconds
- 11. Pressurizer Water Level--liigli Not Applicable h Neutron detectors are exempt from response time testing. Response time of the neutron flux signal portion of the channel shall be measured from detector output or input of first electronic component in channel.
[ (This provision is not applicable to CP's docketed af ter January 1,1978. See Regulatory Guide 1.118, November 1977.) O O ~O
O O O , TABLE 3.3-2 (Continued) [-, REACIOR 1 RIP SYSTEM INSlRUMENTAT10N HLSPONSE IIES FUNCTIONAL UNIT HESPONSE IIME
- 12. Loss of Flow s
A. Single Loop (Above P-8) $ (1.0) seconds j
- 8. Two Loops (Above P-7 and below P-8) < (1.0) seconds i
- 13. Steam Generator Water Level--Low-Low $ (2.0) seconds 414'7 etf' Generp}or di ident ya(erj[tp',
w ,, yty FlosMl4matjh' . Not' Appl'icgble-
- 15. Undervoltage-Reactor Coolant Pumps < (1.5) seconds s
] 16. Underfrequency-Reactor Coolant Pumps < (0.6) seconds e r M 17. Turbine Trip -
A. Low fluid Oil Pressure Not Applicable ' B. Turbine Stop Valve Not Applicable
- 18. Safety Injection Input from ESF Not Applicable
,1NI Ieadtor <Couldit-Pijap-l{tyakei[_Posi[ ion /Ir.j p Not Agelic'ble a
- 20. Reactor Trip System Interlocks Not Applicable
- 21. Reactor Irip Breakers Not Applicable
- u. 22. Automatic Trip Logic Not Applicable C
C#9 40 - ,s
TABLE 4.3-1
'T y REAC10R TRIP SYSlEM INSTRilHENTATION SURVEILLANCE RLQUIREMENTS TRIP ANAL 0G ACluATING MODES FOR CilANNEL DEVICE WillCll CilANNEL CilANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE FUNCTIONAL UNIT CilECK CALIBRATION IEST TES1 10GIC IESI 15 REQUIRE 0
- 1. Manual Reactor Trip H.A. N.A. N.A. R N.A. 1, 2, 3", 4^, S*
- 2. Power Range, Neutron Flux liigh Setpoint S(9) D(2, 4), H N.A. N.A. 1, 2 M(3,4),
Q(4, 6), R(4, 5) low Setpoint S(9) R(4) H N.A. N.A. 1,,,, 2 t' 3.. Power t. ; : . stron Flux, N.A. R(4) H N.A. N.A. 1, 2
** Hl 0 h 6'v. i,ve hoe
'Y
, M 4. Power Ran00, Neutron Flux, N.A. R(4) H H.A. H.A. 1, 2 i liigh Hegative Rate S. Intermediate Range, S(9) R(4,5) S/U(1),H ###
1.A. N.A. 1 ,2 Neutron Flux
- 6. Source Range, Neutron Flux S(9) R(4, 5) S/U(1),N(9) ##
N.A. N.A. 2 , 3, 4 S
- 7. Overtemperature AT S R H N.A. N.A. 1, 2
- 8. Overpower AT S R H N.A. N.A. I, 2
- 9. Pressurizer Pressure--Low S R H N.A. N.A. I j , 10. Pressurizer Pressure--liigh 5 R H N.A. N.A. 1, 2 m
] 11. Pressurizer Water Level--liigli 5 R H N.A. N.A. I
- 12. Loss Of Flow 5 R H N.A. N.A. I i8 G G .
! , O O 4
IABLE 4.3-1 (Continued) i er J. REAC10R TRIP SYSifM INSlRUHfNIATION SURVLILLANCE RtQUIREMENTS d TRIP
. ANAL 0G ACIUAIING N00fS FOR >
CilANNEL DEVICE WHICil ! CilANNEL CllANNLL OPERAT10NAL DPfRAT10NAL ACTUAIlON SURVEILIANCE FUNCTIONAL UNil ClifCK CAllBRATION TEST ILSI LOGIC 1[ST IS REQUIRE 0 ,
- 13. Steam Generator Water Level-- S R H H.A. N.A. 1, 2 Low-tow
~
- 'T *
(deuwafeifl0W MisedtC[
- 15. Undervoltage - Reactor Coolant N.A. R N.A. H N.A. 1 Pumps w
i 16. Underfrequency - Reactur N.A. R N.A. M N.A. I y Coolant Pumps
- 17. Turbine Trip A. Low fluid Oil Pressure N.A. N.A. N.A. S/U(1, 10) N.A. 1 B. Turbine Stop Valve N.A. N.A. N.A. S/U(1, 10) N.A. 1 ,
Closure l l
- 18. Safety injection input from H.A. N.A. N.A. R N.A. I, 2 ESF a fkr
$ ' ' ' *^~ ! '
Y ^' '
~~
- 20. Reactor Trip System Interlocks Mu. A. Intermediate Range Neutron Flux, P-6 N.A. R(4) M N.A. N.A. 2,,
[ B. Iow Power Reactor
- 1 rips Block, P-7 N.A. R(4) M (8) N.A. N.A. I It C. Power Range Neutron flux, P-8 N.A. R(4) M (8) N.A. N.A. 1
TABLE 4.3-1 (Continued) y REAR!0R TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS TRIP
, ANALOG ACTUATING N00ES FOR CilANNEL DEVICE WlICil CilANNEL CilANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION lEST 1EST 10GIC TEST IS REQUIRED D. Low Setpoint Power Rang.~
l Neutron Flux, P-10 N.A. R(4) N (8) N.A. N.A. 1, 2 i E. Turbine Impulse Cliamber Pressure, P-13 N.A. R H (8) N.A. N.A. 1
- 21. Reactor Trip Breaker N.A. N.A. N.A. H (7) N.A. 1, 2, 3*, 4*, 5"
, 22. Automatic Trip Logic H.A. N.A. H.A. N.A. H (7) 1, 2', 3", 4*, Sa l N 1 -
i d u c~ U, CI.D O e 9 -
~ -~ ' ^ - ~ - ~ ~ -
.1-_.
, TA8LE 4.3-1 (Continued) l TABLE NOTATION With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal. N - Below P-6 (Intermediate Range Neutron Flux Interlock) setpoint. Below P-10 (Low Setpoint Power Range Neutron Flux Inter 1cck) satpoint. l (1) - If not performed in previous 7 days. (2) - Heat balance only, above 15% of RATED THERMAL POWER. Adjust channel l if absolute difference greater than 2 percent. (3) - Comoare incore to excore axial flux difference above 15% of RATED THERMAL POWER. Recalibrate if the absoiute difference is greater than or equal to (3) percent. (4) - Neutron detectors say be excluded from CHAMNEL CALIBRATICN. (5) - Detector plateau curves shall be obtained and evaluated. For the Intermediate Range and Power Range Neutron Flux Channels the provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1. O (6) - Incore - Excore Calibration. (7) - Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS. (8) - With~ power greater than or equal to the interlock setpoint the required OPERATIONAL TEST shall consist of verifying that the interlock is in the required state by observing the permissive annunciator window. (9) - Monthly Surveillance in MODES 3*, 4* and 5* shall also include verification that permissives P-5 and P-10 are in their required state for existing plant conditions by observation of the permissive annunciator window. (10) - Setpoint verification is not applicable. 1 O 1 W-STS 3/4 3-15 3gy - 931 _ _._ .__ .._-.. _ __m _-.___--_ -- .-
l i INSTRUMENTATION l 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION l 1 LIMITING 'gDITION FOR OPERATION 3.3.2 The Engineered Safety Feature Actuation System (ESFA3) instrumentation channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their trip l setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4 and with RESPONSE TIMES as shown in Table 3.3-5. APPLICABILITY: As shown in Table 3.3-3. ACTION: *
- a. With an ESFAS instrumentation channel or interlock trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3-4, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setpoint value.
- b. With an ESFAS instrumentation channel or interlock inoperable, take the ACTION shown in Table 3.3-3.
SURVEILLANCE REQUIREMENTS 4.3.2.1 Each ESFAS instrumentation channel and interlock and the automatic actuationlogicandrelaysshallbedemonstratedOPERABLEbytheperformance of the engineered safety feature actuation system instrumentation surveillance requirements specified in Table 4.3-2. 4.3.2.2 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function shall be demonstrated to be within the limit at least once per 18 months. Each test shall include at least one train such that both trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once per N times 18 months where N is the total number of redundant channels in a specific ESFAS function as shown in the " Total No. of Channels" Column of Table 3.3-3. O i W-STS 3/4 3-16 SEP 151981
O C O IABIE 3.3-3
'T
" i
,I INGINEERED SAllIY FEAlllHE AClUATION SYSilH INSIRllHENIAll0N l'
HINIMUM TOTAL NO. CilANNELS CllANNELS APPLICABLE l FUNCTIONAL UNIT OF CilANNELS TO TRIP O_PERAlll E H00ES AC110N
- 1. SAFETY INJECTION, REACTOR TRIP, FEEDWATER ISOLATION, CONTROL R00H ISOLATION, START
DIESEL GENERATORS, CONTAI.WENT COOLING FANS AND ESSENTIAL SERVICE WATER.
- a. Manual Initiation 2 1 2 1, 2, 3, 4 19
- b. Automatic Actuation 2 1 2 1, 2, 3, 4 14 R Logic and Actuat. ion i Relays ;
]e O c. Containment 3 2 2 1, 2, 3 IS*
Pressure-High '
- d. Pressurizer #
4 2 3 1, 2, 3 20^ Pressure - Low
- e. 0.11 terentiai 5<"'" l'i'
- 1, 2, 3" Pressure -Itetuden' AL""'"'I#"
Tteag,Liges-c l{igh c!I-; foys', Loop 2 Plant - four Loops 3/steain linie 2/ steam liste 2/ steam line 15* Operating any steam line u> Q .2/9p'e ra ti ng , .16
- r lopera' ting 11irpd 1003p(7 Qeam' liu' ' e 3/ peratiiid
,any' y/ It'--14S(/ steam
st'eas('l ille ' -
o-operatiog,. g
/ steam'{ine
,!I l; i O
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<weom mu-vw e i M-STS 3/4 3-20 SEP 151981 l
O O O TABLE 3.3-3 (Continued) 8T !-
"4 ENGINEERED SAFE 1Y FEATURE ACTUATION SYSTEM INSTRUMENTATION I; m >
i MINIHilM ' TOTAL NO. CilANNELS CilANNELS APPLICABLE FUNC110NAL UNIT OF CilANNELS TO 1 RIP OPERABLE MODES ACTION SAFETY INJECIl0N, REACTOR TRIP, i FEEDWATER ISOLATION, CONIROL ROOH ISOLA 110N, SIART DIESEL GENERATORS CONIAINMENT COOLING FANS AND ESSENilAL SERVICE WATER (Continued) ; j i1))hrb(Lpogr'P9nt'
~
l.hrce-1,dops r Ture/ l pressure;;- #[ yjib* __, t [l'160ppre)/
.operatingf ;T pressure' cany'2 } oops p ny a 2-loops
'p T -jfp~ressureM;,l griss'ur ..glV i, Opera {tingg opjf loop
M jn]a6y. opes: anyg,e I lyessur,e- [ operating , 4
.- ating loop loop -
l
- 2. CONIAINNENT SPRAY I
- a. Manual 2 1 with 2 1,2,3,4 19 ,
2 coincident ! switches l
- b. Automatic Actuation 2 1 2 1, 2, 3, 4 14 Logic and Actuation Relays
- c. Containment Pressure-- 4 2 3 1, 2, 3 17 liigh-liigh
- i O 3. CONTAINHLNI ISOLATION
*~
- a. Phase "A" Isolation
- 1) Manual 2 1 2 1,2,3,4 19
,o
~
- 2) Sately injection See i above for all Sately injection initiating functions and l requirements .
TABLE 3.3-3 (Continued) y ENGINEERfD SAFELY FEATURE ACTUATION SYSTEH INSTRUMENTATION HINIMUM TOTAle NO. CilANNELS CilANNELS APPLICABLE FUNCTIONAL UNIT Of CilANNELS TO TRIP OPERABLE H0 DES ACTION CONTAINHENT ISOLA 110N (continued)
- 3) Automatic Actuation 2 1 2 1,2,3,4 14 Logic and Actuation Relays
- b. Phase "B" Isolation
- 1) Hanual 2 I wirb-- 2 1, 2, 3, 4 19
-7feelpeident- i y 7witchthr-- '
- 2) Automatic Actuation 2 1 2 1, 2, 3, 4 14
't' Logic and Actuation M Relays
- 3) Contais. ment 4 2 3 1, 2, 3 17 Pressure--liigh-liiall '
- c. Purge and Exhaust Isolation
- 1) Aaitomatic Actuation 2 1 2 1, 2, 3, 4 18 Logic and Actuation Relays j y
- 2) Containment .# /I iW 1, 2, 3, 4 18 Radioactivity-lii 0h m 3) Safety injection See 1 above for all Safety injection initiating functions and Q requirements C#,
O O #
o O O ; TABLE 3.3-3 (Continued)
'T s y ENGINEERED SAFETY FEATURE ACTUATION SYSTIM INSTRUMCWIATION l MINIMUM 1
TOTAL id). CilANNELS CilANNELS APPLICABLE .
. FUNCTIONAL UNIT Of CilANNELS TO TRIP OPERABLE H00ES ACTION l 4. STEAM LINE ISOLAT10N 2 /, h 3
;, sysh m Lew/ 2. 1 23
- a. Manual il, >W<h*d 1/ steam line 1/ steam line 1/ operating 1, 2, 3 24 steam line b Automatic Actuation 2 1 2 1, 2, 3 22 Logic and Actuation Relays
- c. Containment Pressure-- 4 2 3 1, 2, 3 17 i liigh-liigh j D d. ,St3!amf low 2in-4w6 d'Id'W ## *"' #' d,% 3, f !
w Steqa. Lines-Atigh ~' 25 " " #"A - #'M
~
N fi')'-fdurToop. Plant- , 3 x ~ l Four Loops E steam line F/ steam line T/ steam line IS^ i i Operating /4 any 3 steam ilnes jn
.ti[Y,Ihreeg Loop'glant ~
(27stega'l{ne -J/st' epa Jinje' . - 1/ steam-lipe' ..lS*- m / Op]enatiiv.IJhreefL'ogps - any-j!-sleam s
" lines Twoloops i6 l##$ A / operating -16 #'
d/operakne,3
~
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e s ra rp p3 p s e / p o t a
. 2 A O .
io s S TF o 1;10 - / O g 'r -l 1 e 3 D ," E R w E ) o V E d L N e - 't n I u e n a nn G N i n r u J a } P y oo ii [ t n o C t ( i he P s s r P B o p s pg eg on oi t p.-
- o. a l p
o o i y g f, _ g on pp o N O r o t - a-tt aa uu t t cc N e Lt a iH=a e g s' r Lo t]f I T A rl ee AA O t n L'r rr c a &l I
=
i u ue op ;p
=. e h
r jr hl 3 o;w 1e r PS o nvh e e. ig cd i n T A !
, L 3 fO T- O- TM Gf i t a a
h f J T,O I I R mr- l mcy T I N U L O S r c. I i t m a e P L f
/ TR EI E
aeli et g t ai oia t gl uoe a S i f i NA SWli AI R L E C J I W A N BD N I , RE O L 7 . UE O I T M 0 e TF a b C A N E U T . F S S y w1 wA* - uS ,_ c. dm n r
;i - ,,i ;i
IADLE 3.3-3 (Continued} 19 l [-4 ENGINEERED SAFETY FEA1URE ACIllA110N SYSTEM INSTRUNENTATION HINIMUM 10TAL NO. CllA!!;1ELS CilANNELS APPLICAlllE FilNCTIONAL UNIT OF CilANNELS 10 IRIP OPERAlll E H0 DES ACTION
- 6. AUXILIARY FEEDWATER
- a. Manual Initiation 2 I 2 1,2,3 23
- b. Automatic Actuation Logic 2 1 2 1,2,3 22 and Actuation Relays
- c. Sim. Gen. Water Level-Low-Low -
w
- D 1. Start Motor- V .7 84-w Driven Pumps 2'/sta. gen. 2/sta. gen. :2/stm. gen. 1, 2, 3 4ff* ##
4 in any opera- in each ting sta gen. operating sim. gen.
- 11. Start Turbine- y 3 e Driven Pump 7/sta. gen. 2/stm. gen. 2'/sta. gen 16* 2 0 1, 2, 3 in any in each 2 operating operating
- d. A ., .fA ,- ra./whe suc t,2 ir ,/fv s>u ra - it W st , gen, st,, gen 4r--UndervoltaDe-RGP Y "I .2/f -/ .2/jsey /, 2, 3 Af o Sta rt-Turbitte-
.Dr4ven-Pump- A-1Ams ---2-- + t -20' un e. Safety injection Q Start Motor-Driven Pumps - and Turbine-Driven Pump See I above for all Safety injection initiating functions and a requirements m
S f. Station Blackout 4 /),, , Start Motor-Driven Pumps g_ g "* , ,9,, . 4
. c /, , Ja . Et and Turbine-Driven Pump 2 -t 1, 2, 3 49' O O O
l i j TABLE 3.3-3 (Continued) i 8T l } ENGINEERED SAFETY FEAluRE ACTUATION SYSTEM INSlRUMLHIA110N i: HINIMUM l TOTAL NO. CllANNELS CilANNELS APPLICABLE ! FUNCTIONAL UNIT OF CilANNELS TO TRIP OPERABLE MODES ACTION AUXILIARY FEEDWATER (continued)
- g. Trip of Hain Feedwater Pumps Start Motor-Driven Pumps and Tu. ;, i . G-;..a " r 2/ pump 1/ pump 1/ pump 1, 2 # J9- M
- 7. AUTOMATIC SWITC110VER To na CONTAINMENT SUMP k 3
.L
- a. '- '
y RWST Level _ 4' 2 4- 1, 2, 3, Jt' 17 D -- = : ..c:=t=wm
- raa' e ! r:r.t-Sump-
<taval M ig4 + -- --l , 2 ,- 3 . - 4 4 -+7-
-And-dafet3rfnjection- -See-1-above-for-Safety-Injection initiating functions and -
re,7 1 r- _ e_s
- b. Automatie-AetuaLion - 2 + --e-- 1, 2 ;- 3, _A 2. ~14-
-Logle-and-Aetuatio %
-Relays-un 9 8. LOSS OF POWER m 4/L; . -1,~ 2 , 3 , '
- aH-kv-H us - - 2/ h 3/Bu:n -208-in m
-toss-o f-Vol lege.-
3 4
'7 - D. Grid Degraded Voltage d/ Bus 2/ Bus -3/ Bus 1, 2, 3, 4 20"
.-Qa n j:n l _ L ;'y; ;, :: "i-- )
TABtE 3.3-3 (Continued)
"a ENGINEERED SAFETY FEAIURE ACTUATI0il SYSTEM INSIRUMENTATION HINIMUM 10TAL NO. CllANNELS CilANNELS APPLICABLE FUNCTIONAL UNIT OF CilANNELS TO TRIP OPL HABt E N00ES ACTION
- 9. ENGINEERED SAFE 1Y FEATURE ACTUATION SYS1EH INTERLOCKS
- a. Pressurizer Pressure, 3 2 2 1,2,3 21 P-ll
- b. Low h T, , P-12 4 2 -
3 1,2,3 21
- c. Reactor Trip, P-4 2 2 2 1,2,3 23 R
+
M i 1 1 (A Y G O 9 --
O - TABLE 3.3-3 (Continued) TABLE NOTATION
#Trip function may be blocked in this MODE below the P-11 (Pressuri:er Pressure Interlock) setpoint.
i Trip function may be blocked in this MODE below the P-12 (Low-Low T Interlock) setpoint. **9 The channel (s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the trippec mode.
*The provisions of Specification 3.0.4 are not applicable.
ACTION STATEMENTS ACTION 14 With the number of CPERA8LE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STAN08Y within 6 hours and in COLD SHUT 00hN within the following 30 hours; however, one channel may be bypassed for up to 2 hour for surveillance testing per Specification 4.3.2.1, provided O the other charnel is OPERA 8LE. ACTION 15 With the number of OPERA 8LE channels one less than the Total Numcer of Channels, operation may proceed until performance of tne next required OPERATIONAL TEST provided the inopersole channel is placed in the tripped condition within 1 hour. ACTION 16 With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours or be in at least HOT STAN08Y witnin the next 6 hours ard in at least HOT SHUTDOWN within the following 6 hours. One l channel associated with an operating loop may be bypassed for 1 up to 2 hours for surveillance tasting per Specification 4.3.2.1. ACTION 17 With the number of OPERA 8LE channels one less than the Total Number of Channels, operatfort may proceed proviced the inoperaole channel is placed in the ' condition and the Minimum Channels OPERA 8LE requirement is met. On; :::iti:n:1 :h;ane' ry,t ;,,y.r.,14 c44= e/ may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.2.1. ACTION 18 - With .less than the Minimum Channels OPERABLE requirement, operation may continue provided the containment purge supply and exhaust valves are maintained closed. l O W-STS 3/4 3-29 SEP i 519% i
_ __ _ _ _ _ . . _ _ _ _ _ Z J. __. _ _ __. i TABLE 3.3-3 (Continued) , ACTION STATEMENTS (Continued) ACTION 19 - With the number of CPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours or be in at least HOT STAN08Y within the next 6 hours and in COLD SHUTD0hN within the following 30 hours. ACTION 20 - With the number of OPERABLE channels 3ne less than the Total Number of Channels, STARTUP and/or P0hER OPERATION may proceed provided the following conditions are satisfied:
- a. The inoperaole channel is placed in the tripped condition within i hour.
- b. The Minimum Channels OPERABLE requirements is met; however, f4 e /nep m M- -4ae-additiond channel may be bypassed for up to 2 hours for surveillance testing of other channels ;:er Scecification a.3.2.1.
ACTION 21 - With less than the Minimum Number of Channels OPERABLE, within one hour determine by observation of the associated permissive annunciator window (s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.O.3. ACTION 22 - With the numcer of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STAND 8Y within 6 hours and in at least HOT SHUT 00hN within the following 6 hours; however, one channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.2.1 provided the other cnannel is OPERA 8LE. ACTION 23 With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperaole channel to GPERABLE status within 48 hours or be in at least HOT STAND 8Y within 6 hours and in at least HOT SHUTDOWN within the following 6 hours. 1 ACTION 24 With the number of OPERABLE channels one less than the Total l Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours or declare the associated valve inoperaDie and take the ACTION required by Specification (3.7.1.J0 4 l 9 SEP 15181 W-STS 3/4 3-30 ,
t TABLE 3.3-3 (Continued) M t e '=b of OP RABLE ch- .e l ne less n the ' ta er f ' nnel estor e V erabl nnel t .. A [ t n s "' in
- ACT
,ours req (i e
by r tn so ated cifica io . 7.1. in 2f c7
. Ac7Ior; m With tne numoer of OPE?ABLE cnannels less tnan the total nurser of channels, restore the inocerable cnannels to OPERABLE status within 48 hours or declare the associated auxiliary feedwater pump inocerable and take the ACTI0tt recuired by Scecification 3.7.1.2. With channels associated witn more tnan one cuma inocerable, immediately declare tne associated auxiliary feedwater cumos inocerable and take the ACTIO:t recuired by Scecification 3.7.1.E.
J 7 - McGUIRE - UNIT 1 3/4 3- Z AME:lCtEili;Cg3 Q) arr 2 xa jsnaie-
- -- - - . . - , , . . , . -, .- ,- - - - y- _ --
1 i O O O TABLE 3.3-4 i 'T i "e ENGINEERE0 SAFETY FEATURE ACTUATION SYSTEM INSTRUMENIA110N TRIP SE1 POINTS FUNCTIONAL UNIT TRIP SETPOINT Att0WABIE VALUES
- 1. SAFEIY INJECTION, REACIOR TRIP, t FEE 0 WATER ISOLATION, CONTROL R00H ISOLATION, i
START OIESEL GENERATORS, CONTANNENT COOLING FANS AND ESSENTIAL SERVICE WATER. i a. Manual Initiation' Not AppIlcable Not Applicable
- b. Automatic Actuation Logic Not Applicable Not Applicable and Actuation Relays
! // /. 2 j c. Containment Pressure--liigh 5 Sepsig 1 Sr5 psig 1 /9 'tJ~ /93F
- d. Pressurizer Pressure--Low 1 N E psig 14M6 psig 1
w e. -94+fe.e..iial Pressure- < ! ^^ p i W12-psi-b*e,"E$'febs'u'r': "bw M "'N / Mf"5
-f. SL. T! .: in--Two-Stear-idnes-- c A-fu ti fined as
-High- -+ A-f us)ction-defined-as-j 26J. ' orrIy ,[oll' s- 'N Ap copelponjin[,
sp,' f full 4 t,V 4 ull'lteas-{lbw '/ f 6e pw , , the n'd afd)D4)13ad patt 20% op. n'
- P t pa r astog l}n_garl crepy ~ 1;, ar,lyy' ,Ap ts6a;Ap,c ' sponiting'Lo c ng tyvf 'I fil,$r ftp l-steam flow I spg(as
$ pow fuHa fdll oad '
, a-Coinc4 dent-WittritusF 1
I
$ <helytar-tow,-or ' 1 ct:% gt20a.t n . ./=
2 steam-t4ne*Prersucu% + gaategg -7=(sea >=,mit E 4
1ABLE 3.3-4 (Continued) y ENGINEERED SAFETY FEA1URE ACTUAIl0N SYSTEM INSlRUHENIAIlON 1 RIP SETPOINIS FUNCTIONAL UNIT TRIP Sf1POINI ALLOWABLE VALUES
- 2. CONTAINHENT SPRAY i'
- a. Manual Initiation Not Applicable Not Applicable
- b. Automatic Actuation Logic Not Applicable Not Applicable and Actuation Relays 2.7 3. c
- c. Containment Pressure--liigh-High 5 (25) psig 5 ( R ) psig ,
- 3. CONTAINHENT ISOLATION y a. Phase "A" Isolation
+
y 1. Manual Not Applicable Not Applicable
- 2. Saft.ty Injection See 1 above for all Safety injection Trip Setpoints/
Allowable Values
- 3. Automatic Actuation Logic Not Applicable Not Applicable and Actuation Relays
- b. Phase "B" Isolation
- 1. Manual Not Applicable Not Applicable
- 2. Automatic Actuation Logic Not Applicable Not Applicable and Actuation Relays
.,;. 7 3.0
- 3. Containment Pressure--liigh-liigh 5 (.20) psig 5 (F2) psi 0
{ CJ9 U O O O
~ . - _ _
{ O O O I ! 'T TABtE3.3-4(Continued) l y ENGINEERED SAFETY FEA1URE ACIUATION SYSTEM INSTRUMENIA110N TRIP SE1P0lNIS l i FUNCTIONAL '911T TRIP SEIP0lNT Att0WABLE VAtuES $ CONTAINNENT ISOLATION (continued) l c. Purge and Exhaust Isolation
- 1. A'utomatic Actuation Logic Not Applicable Not Applicable
! and Actuation Relays
- 2. Containment Radioactivity--liigh ($ 2 x background) ($ 2 x background)
- 3. Safety Injection See I above for all Safety Injection Trip Setpoints/
- 9. Af<mu r/ Allowable Values . ,
,pf 1,;,v,a. ;ja
. Ar/ AgrA2",N R
- 4. STEAM LINE ISOLATION I 'f a. Manual Not Applicable Not Applicable O
- b. Automatic Actuation Logic Not Applicable Not Applicable and Actuation Relays a'. '/ ~L C
- c. Containment Pressure--liigh-liigh $ (20) psig 1 (R) psig
- d. hieTwa Steam Lines- .
< A function defingd as -- - < A-func}Jon defined ps -
4tigh. 7 l'lf Wrespond j e J611ogr A ApIcorre' spor}djnfj ful M team -steam 41oG.b < tween,ITO dhTl.20%21 /.. /-3 :9 f4jfull.b
'd'-g %rTg~adan'j d'andphfiiffA? is . tier 'isidrjssihg'line3rJy, 3
' g iskj 1Jnay16ty%pA$yr'eas-
'sppjs ul 5
,t6 1:0 .or c
y rre- Va 111. ITespondinf-t f gl l'-s te,am ow at
, stea owatjull'3ull load fur .. load fE g, .g;p & S/c e~r L4/e -< -- g e p.s 7/yec c - / 4't' /~ "b c o'
p,,,, u y a ,p,fc -- /,r,y// ' - y&,y s.,7 l r ',7 *~ f/ e' D WE ~ W *
- o' Y 1
i W
TAllLE 3.3-4 (Continued) y ENGINEEREO SAFETY FEA1URE ACTUATION SYSTEH INSTRUMENIA110N 1 RIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINI ALLOWABLE VALUES
--ST EAM-H NE-I SOLAT4 ON-( conti nued )-
c -Coincident-if f th-Either-i
- 1. T '
- 5 aVD 6
-2. Steam-bine-Pressure- Luw i-(600)-psig- -+-(S80)-ps ig-
- 5. TURBINE TRIP AND FEE 0 WATER ISOLATION Sa #3
- a. Steam Generator Water level-- < (67)% of narrow range < (48)% of narrow range liigh-liigh , 7-/P Instrument span each steam Instrument span each steam y Generator Generator w b. Automatic Actuation Logic Not Applicable Not Applicable :
i g and Actuation Relays
- 6. AUXILIARY FEEDWATER j
- a. Manual Not Applicable Not Applicable
- b. Automatic Actuation Logic Not Applicable Not Applicable and Actuation Relays pye f- [c.
1 Steam-Geneeator-
-Water-level-Lew-Lthe P(10)% Ur rlarrow range Instrument-span-each-
=->-(9)% nf narrow-range-
-Instrument-span-each-
. steam-generator- -steam generator -
h -d -Under-voltage--RCP- ~t(-70)%-RCP-bits-vol taga- i (69)%-RCP-bus-voltage- [, e. Safety Injection See 1 abnve for all Safet.v Injection Trip Setpoints/ Allowable Values O 9 9
8 m k- s l TABLE 3.3-4 (Continued) c ENGINEERLD SAFETY FEATURE ACIUA110N SYSlfM INSTRUMINIA1_10_N 1 RIP. SElP0lNTS - S A FUNCIlONAL UNIT TRIP SElPOINI All0WABLE VALUES 6MIRBINE-Trig AND: FEED c/Wpn fRf1303TJON'
,{p' (;-g M ttam ~Taenerafo? Wgtpp- 82% of fla pr yngs y p' 3 of narsew ra p giflijl190V instris ent"s '1L 1D5 ruipeff[ Span ~ eaCl}c o hm' u team en6hr/ '~~'
~
}3 pgetfoi./panf'dCh5 67 iffAl N[ PRE 550R M 0E-O STE [
gT,ihlset%e- 5 0.25 psid $ 0.25 psid ; [44yr13 err 1 0.25 psid 1 0.25 psid ,
-7. AUX !LIARY-F EEi",.2TER R* e. Manual ~Not-AppMcalde -Not-Appio rible
,~A--Automatic-Actual 4en-tope- .____ _
-Hot-Appi leable _'--Not-AppMcable_.- _ _ . - _ _ _
- c. Steam Generator > 12% of span from 0 to > 11% of span from 0 to 'N Water Level--Low-low 30% of RATED TilERMAL POWER, 30% of RATED lilERMAL POWER, increasing linearly to increasing linearly to l
> 54.9% of span at 100% of > 53.9% of span at 100% of -
HA1ED TilERMAL POWER. RATED lilERMAL POWER. - 4 -== = 5a k . % / ?z ':;/- ' > - 6 I above (ai!-SI-Sctpaints)f,f'2-. '? eC-
-4. Station-Blackout- < 3 :C4 - 173 --volts =with a-
~
- ' 3200 =! t&-
--48 :5 _ 0. 5 = send-bime=delsy, --
j Me -4, W Auxiliary feedwater ' s Suction Pressure - low > 2 psig > 1 psig )
-0 _ --Teip-of-Main-Leedwater-. Pump > -Not-Appfisable - Not-Applicable- ;
i 6 e 4
O i i l TABLE 3.3-4 (Continued) ! ' *f
,4 ENGINEEREI) SAFETY FEATURE ACIUATION SYS1EH INS 1RUMENIATION TRIP SEIP0lNIS FUNCTIONAL UNIT TRIP SETPOINT A110WAlllE VALUES PhEA 7 93 ,t. 5 .seec...!s $. ~/'
-iN' l'< /A 5
! AUXILIARY FEEDWATER (continued) , li
- f. Station Blackout -t-(-)%-Transfer-Bus .VoltageW-)t-Transfer-Cas Voltage
! g. Trip of Main feedwater Not AppIlcable Not Applicable Pumps
- 7. AUTOMATIC SWITCHOVER TO CONTAINMENT SUMP '
g im s 7 c ;,., i. , . .
- a. RWST Level % ~> (4-30!L)drom-tank-base- > (126u.)-f rom.. tank -base-
-C-oincident-With-
- C;;t Laat ';w 1.evel- -High 5 (3n") ahave elevr (680') 5 (32r58-)-above-elev-(680L)
'f and -
--Safety-injection.-- -See--l-above-for- all Saiety Injection-Trip Setpoints/ ----.-
*-Allowable-Values) -
- h Automatic- Actuation- Logic-- Not App 11 cable NoL Applicable
. -and-Actuatios s " lays _._
- 8. LOSS OF POWER f
.a.---446 kw Emenemy M 'Ja'8ervalty,;c - ( 1 )-volts-with a --(-t--)-volts -wi th a-(Lost, af Valt.;4 -(-+--)-second-time-deIay-- r:(:-+---}-second- timo dolay -
a 'l6 't i7J
-7, an 4.16 kV Emergency Bus Undervoltage () i A) volts with a -(-*-)-vol ts- wi th a- .
m (Degraded Voltage) (, 1 ) second time delay (--+-)-second - time-de l ay-EU .C.5 A R ,, g >- 3 A*. W// >
~
t,19 . (D l
! ! I 9
'y
) Y' '
5 4 S ( D I' S E t l g 4
- e f
/" '
l d l A i n b V s a a ~~- S 1 E g p F i c - ' N
")
_ L l ~ _ I H , p O A )M i4 p
~=
P W 0 0;4 A ^: l 2 s(4 E l ( ' t S l o A 1 > N P I R I l l 0 1 1 Al l ~
/ '
i f .# H ,
) U
)
d R .3 , Eb e l e u S T g l - 7 n N N A fy i i I I s a ' t n o H O P _ p 2 i c a Y L' C ( 4 E T S Y S l E S P I
)
0 0 0 2 {
)
3 4 f l A t p c p S
/
c; '- 9 3 N R o a 3. O I T $ 5 ( N
'f =
T 4 E L A U 7 B A l C N T A e E C R U N 9' T O / A I E T - f Y A U l 1 1
/ D W
r C P uU T
E A / F , A E e s S D E R U T A r u s s 2 1 4 t c WI
/
n e R E e P P r E F r - } E N YS P , g p , 6, 7 / 8 A'< I lK r y i G EC e , r . t ~< N FO z T T v ;- E AL SR i r u r o s w, fr , E z T I N DT EN RI s s e r ht w o c a a
- ;4 f
s a a T r U L A N E EM NE I T GS P L e R y. s m, c O NY . . .
/. q J ES a b c 9
I T C . N U p F 9 y y* w "* mo Hv. O6
V TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS
- 1. Manual
- a. Safety Injection (ECCS) Not Apolicable ceecwater Isolation Not Applicable Reactor Trip (SI) Not npolicable Centainment Isolation-Phase "A" Not Applicable Auxiliary Feedwater Pumos Not Applicable Nuclear Servica Water Systam Not Applicable Centain.;:ent Air Recirculatien Fan Not Applicable
- b. Containment Scray Not Apolicable Centainment Isolation-Phase "S" Not Applicable Containment Vent and Purge Isolation Not Applicaole Annulus Ventilation System Not Applicable
- c. 00ntainment Isolation-Phase "A" Not Applicable Containment Vent and Purge Isolation Not Applicable
- d. Steam Line Isolation Not Acolicable
- e. Purge and Exhaust Isolation Not Apclicable l
- 2. Containment Pressure-Hioh
- a. Safety Injection (ECCS) 1 27.0(1)
- b. Reactor Trip (from SI) 1 2.0 l c. Feedwater Isolation < 9.0
- d. Containment Isolation-Phase "A" (4) 1 18.0(5)/28.0(6)
- e. Containment Vent and Purge Isolation Not Applicable
- f. Auxiliary Feedwater Pumps Not Applicable
- g. Nuclear Service Water System 1 65.0(5)/76.0(6)
- h. Component Cooling Water System 1 65.0(5)/76.0(6)
- 3. Pressurizer Pressure-Low
- a. Safety Injection (ECCS) 1 27.0(1)/12.0(5) l m b. Reactor Trip (from SI) < 2.0 McGUIRE - UNT.T 1 3/4 3-M t/ N z 7 > 37
TABLE 3.3-5 (Continued) ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECCNDS
- c. Feedwater Isolation 5 9.0
- d. Containment Isolation-?hase "N' (4) ;19.0(}/29.b5}
- e. Containment Vent and Purge Isolation Not Applicable
- f. Auxiliary Feedwater Pumps Not Applicacie
- g. Nuclear Service Water System < 76.0C )/65.CC)
- h. Componenti Cooling Water - System 76.0(1)/65.0 )
4 Necative Steam Line Presse e Rate "ica
- a. Steam Line Isolation < 9. ]
- 5. Steam Line Pressure-Low
- a. Safety Injection (ECCS) $ 12.0( )/22.0C)
J
- b. Reactor Trip (from SI) 5 2.0
- c. Feedwater Isolation < 9.0
- d. Containment Isolation-Phase " A" (a) 18.0()/28.dO)
- e. Containment Vent and Purge Isolation Not Applicable
- f. Auxiliary Feedwater Pumps Not Apolicaole
- g. Nuclear Service Water System < 65.0(5)/76.0(6)
- h. Component Cooling Water System 65.0(5)/76.0(6) i Steam Line Isolation i 9.0
- 6. Containment Pressure--High-Hich
- 3. Containment Spray 5 45.0
- b. Containment Isolation-Phase "B" Not Applicable
- c. Steam Line Isolation i 9.0
- d. Containment Air Recirculation Fan 1 610.0
- 7. Steam Generator Water Level--Hich-High
- a. Turbine Trip Not Aoplicable f' b. Feedwater Isolation 1 13.0 V
l McGUIRE - UNIT 1 3/4 3-N W N r 7' .2- M 1 l ,, -
TABLE 3.3-5 (Continued) ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIMES IN SECONOS
- 8. Steam Generator Water Level--Low-Low
- a. Motor-driven Auxiliary i 60.0 Feedwater Pumps
- b. Turbine-driven Auxiliary 1 60.0 Feedwater Pump
- 9. Station Blackout
- a. Turbine-driven Auxiliary i 60.0 Feedwater Pump
- b. Motor-driven Auxiliary i 60.0 Feedwater Pumps Op 10. RWST Level
'a
- a. Automatic Switchover to Recirculation 1 60.0
- 11. Trip of Main Feedwater Pumos
- a. Motor-driven Auxiliary Feedwater Pumps 1 60.0 Note: Response time for Motor-driven
' 1 60.0 Auxiliary Feedwater Pumps on all S.I. signal starts l
l l b)
\s McGUIRE - UNIT 1 3/4 3-26 AIne'ddmentJof 7 f/NZ Y L JT A1Q127/81' s
TABLE 3.3-5 (continued) TABLE NOTATION (1) Ofesel generator starting and sequence loading delays included. Response time Ifmit includes opening of valves to estaD11sn SI path and l attainment of discharge pressure for centrifugal charging pumps, SI and RHR pumps. g c ,,,,, ,,,,, , , g , y, (4) Valves IXC3058,ame 1XC315Bjare exceptions to the response times listed in the table. The following response times in seconds are the required values for these valves for the initiating signal and fuwtion indicated:
- 2. d 5) 3.d <30.0(5)/a0.0(6) 730.0(
- 5. d 530.0(5)f.0.0(6)
(5) Ofesel generator . tarting and secuence loading delays g included. Of fsite power available. Response time limit includes opening of valves to esta:1'=h SI path and attainment of discharge pressure for centrifugal charging pumps. (6) Ofesel generator starting and sequence loading delays included. Response time 11: nit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumes. l 1 - G '- 1 W McGUIRE - UNIT 1 3/4 3-14
- /NZ r 2-i ._
V) \\ \ TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONOS
- 1. Manual
- a. Safety Injection (ECCS) N,ot Applicable l b. Containment Spray Not Applicable
- c. Containment Isolation Phase "A" Isolation , Not Applicable Phase "B"' Isolation Not Applicble
/
Purge and Exhaust Isolation ,'
,/ Not Applicable
- d. Steam Line Isolation ,
Not Applicable
- e. Feedwater Isciation ,- Not Applicable
- f. Auxiliary Feecnater Not Applicable lyuehar
- g. -::::nt GService Water d
Not Applicable h NbNt- Cco l i ng h ** ~ " Not Applicable ,
- i. Cum.rai Avv. I 5 v l at.+3nd :;ct Appli;ab':-
l( 2. Containment Pressure-High
- a. Safety Injection'(ECCS) N < (27.0)(1)/(12)(5)
- b. Reactor Trip (from SI) < (2.0)
- c. Feedwater dlation (9.0)(3)
- d. Contiin t Isolation-Phase "A" (MO)(2)/([0)(1)
- 6. ContaipbntVentandPurgeIsolation '25.C)N'(10.0) ,flh/4
- f. Auxi[iar '
g. p- /ha y Feedwater Pumps
-- ' <ervice Water System sS-N)'O'd'I'#"#"
< (4 0) ) (74+P.0)(1)
E .0)(1)/( 0)(2)
- h. r :n.lE E $;,.t Cooling A ns(* *<
N C trel "::: Isciatiem
.-MM A;;110:bl:
J s x Q (2/C cf C 60 O V PSTS 3/4 3-37 SEP 151981
6 g6 f{
"y v TABLE 3.3-5 (Continued) 1 ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL A50 FUNCTION RESPONSE TIME IN SECON05
- 3. Pressurizer Pressure-Low
- a. Safety Injection (ECCS) 5 (27.0)(1)(12.0)(5)
- b. Reactor Trip (from SI) 1 (2.0)
- c. Feedwater Isolation 1 (7.0)(3)
- d. Containment Isolation-Phase "A" 1 (17.0)(2)/(27.0)(1)
- e. Containment Vent and Purge Isolation 1 (25.0)(1)/(10.0)(2)
- f. Auxiliary Feedwater Pumps 1 (60.0)
- g. Essential Service Water System 1 (47.0)(1)/(32.0)(2)
- h. Containment Cooling Fans 5 (55.0).(1)/(40.0)(2)
- i. Control Room Isolation Not Acplicable
- 4. Differential Pressure Between Steam Lines-High
- a. Safety Injection (ECCS) 1 (22.0)(4)/(12.0)(5)
- b. Reactor Trip (frcm SI) < (2.0)
- c. Feedwater Isolation (7.0)(3)
- d. Containment Isolation-Phase "A" 1 (17.0)(2)/(27.0)(1)
- e. Containment Vent and Purge Isolation 1 (25.0)(1)/(10.0)(2)
- f. Auxiliary Feedwater Pumps 1 (60.0)
- g. Essential Service Water System 1 (32.0)(2)/(47.0)(1)
- h. Containment Cooling Fans 1 (55.0)(1)/(40.0)(2)
- 1. Control Room Isolation Not Applicable
- 5. Steam Flow in Two Steam Lines - High Coincident with T --Lew-Low Safety Injection (ECCS) 1 (24.0)(4)/(14.0)(5)
- b. Reactor Trip (from SI) 1 (4.0)
- c. Feedwater Isolation 1 (9.0)(3) l d. Containment Isolation-Phase "A" 1 (19.0)(2)/(29.0)(1)
- e. Containment Vent and Purge Isolation 5 (27.0)(1)/(12.0)(2) I
- f. Auxiliary Feedwater Pumps 1 (60.0)
- g. Essential Service Water System 1 (34.0)(2)/(49.0)(1)
- h. Steam Line Isolation 1 (9.0)(3) 1./ Containment Cooling Fans 1 (57.0)(1)/(42.0)(2)
J. Control Room Isolation Not Applicable , 1 l y-STS 3/4 3 38 SEP 15 Gat
Sa,a m du/ TABLE 3.3-5 (Continued) ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECON05
- 6. Steam Flow in Two Steam Lines-Hich Coincident with Steam Line Pressure-Low
- a. Safety Injection (ECCS) 1 (12.0)(5)/(22.0)(#)
- b. Reactor Trip (from SI) 1 (2.0)
- c. Feeowater Isolation 1 (7.0)(3)
- d. Containment Isolation-Phase "A" 1 (17.0)(2)/(27.0)(1)
- e. Containment Vent and Purge Isolation -< (25.0)(1)/(10.0)(2)
- f. Auxiliary Feedwater Pumps 1 (60.0)
- g. Essential Service Water System 1 (32.0)(2)/(47.0)(1)
- h. Staam Line Isolation 1 (9.0)(3)
- 1. Containment Cooling Fans 1 (55.0)(1)/(40.0)(2)
- j. Control Roca Isolation Not Applicable
- 7. Containment Pressure--High-High ,
- a. Containment Spray 1 (45.0)(2)/(57.0)(1)
- b. Containment Isolation-Phase "B" 1 (65)(1)/(75)(2)
- c. Steam Line Isolation 1 (9.0)(3)
- 8. Steam Generator Vater Level--High-Hich
- a. Turbine Trip 1 (2.5)
- b. Feedwater Isolation 1 (7.0)(3)
- 9. Steam Generator Water Level - Low-Low
- a. Motor-driven Auxiliary Feedwater Pumps 1 (60.0)
- b. Turbine-driven Auxiliary Feedwater Pumps 1 (60.0) l
- 10. Containment Radioactivity - High
- a. Purge and Exhaust Isolation 1 (25.0)(1)/(10.0)(2)
O pSTS 3/4 3-39 . SEP 15 ic81 l -- . . - .
g( ((Cd TABLE 3.3-5 (Continued) ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS
- 11. RWST Level-Low Coincident with Containment Sumo Level-Hicn and Safety injection
- a. Automatic Switchover to Containment Sump 1 (250)(2)/(265)(1)
- 12. Undervoltace RCP
- a. Turbine-driven Auxiliary Feecwater Pumps 1 (60.0)
- 13. Station Blackout
- a. Auxiliary Feedwater Pumps 5 (60.0)
- 14. Trio of Main Feedwater Pumos
- a. Auxiliary Feedwater Pumas Not Applicable l )
- 15. MssofPcwer
- a. 4.16 kV Emergency Bus 1 (10)
Undervoltage (Loss of Voltage)
- b. 4.16 kV Emergency Bus 5 (10)
Undervoltage (Oegraded Voltage) i I O W-STS 3/4 3-40 SEP 151981
a._ - _ TA8LE 3.35 (Continued) TABLE NOTATION (1) Diesel generator starting and sequence leading delays included. (2) Diesel generator starting and sequence loading delay not includea. Offsite power available. (3) Air operated valves (4) Diesel generator starting and sequence loading delay included. RHR pumps not included. (5) Ofesel generator starting and sequence loading delays not included. RHR pumps ng included. . C-ll,PE-We4k.c=f
/
O l l O l 15 G31 W-STS 3/4 3-41 i
I Alll E 4. 3-2 - sy ENGINEERLD SAFETY FEAlllRE AClllA110N SYSIIH INSIRllHENIAll0N q SURVETTFANCE REQOTREHENTs vs 1 RIP ANALOG ACTUAlING N00ES CilANNEL DEV1CE MASTER SLAVE FOR WillCil CilANNEL CilANNEL OPERATIONAL OPERATIONAL ACTUAT10N RELAY RELAY SURVEILLANCE . FUNCTIONAL llNIT CilECK CAllBRAll0N 1EST lLSI 10Glc 1EST lEST 1EST IS REQUIRED
- 1. SAFETY INJECTION, REACTOR TRIP FEEDWATER ISOLATION, CONTROL R00H ISOLATION START DIESEL GENERATORS, CONTAINHENT COOLING !
FANS AND ESSENTIAL SERVICE WATER
- a. Manual Initiation N.A. N.A. N.A. R N.A. N.A. N.A. 1, 2, 3, 4
- b. Automatic Actuation H.A. N.A. N.A. N.A. H(1) H(1) Q 1, 2, 3, 4 i Logic and Actuation I Relays
, l' D c. Containment Pressure- S R H N.A. N.A. N.A. N.A. 1, 2, 3 y lii0h Ng d. Pressurizer Pressure- S R H N.A. N.A. N.A. N.A. 1, 2, 3 !
N low i I
- e. Diffacath! arm... c S R H N.A. N.A. N.A. N.A. 1, 2, 3 htween Steam 44nes-
.y4 3 % i,;, < & nm - L *w
-f --5 thin imu Stem 5 -R H N;A. N.A. N.A.- - N . A .-- --- I .-2 r -Hues =lligtt-foincident
-Witii Eiiner
. -- L Y --!ow= tow;--or S R H- N.A. N. A.- - - N. A. N.A. -- 1, 2 ; -3
-2,--S t ean-L-i ne-- S R H N.A. N.A. N.A. N.A. 1, 2, 3 -
-Pres ure-d o w e
- 2. CONTAINHENI SPRAY i
M a. Manual Initiation N.A. N.A. N.A. R N.A. N.A. N.A. 1, 2, 3, 4 )
- b. Automatic Actuation N.A. N.A. H.A. H.A. H(1) N(I) Q 1, 2, 3, 4
- u. Logic and Actuation m Relays oo
- c. Containaiesit Pressure-- S R H H.A. N.A. N.A. N.A. 1, 7, )
liigh-llioli O O O
O O O TABLE 4.3-2 (Continued) 8T ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION g SURVETITANCElf0llIREHERT5 TRIP ANALOG ALTUATING N00ES CilANNEL llEVICE MASTER SLAVE FOR WilCll CilANNEL CilANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE FUNCIl0NAL UNII CilECK CAllBRATION IFSI TEST 10Glc TESI TEST TEST IS REQUIRED
- 3. CONTAINNENT ISOLATION
- a. Phase "A" Isolation
- 1) Hanual N.A. N.A. N.A. R N.A. N.A. N.A. 1, 2, 3, 4
- 2) Safety injection See 1 above for all Safety injection Surveillance Requirements
- 3) Automatic Actuation N.A N.A. N.A. N.A. M(1) H(1) Q 1, 2, 3, 4 w logic and Actuation i Relays
- b. Phase "B" Isolation
-L I) Manual N.A. N.A. N.A. R N.A. N.A. N.A. I , 2, 3, 4 fJ
- 2) Automatic Actuation N.A. N.A. N.A. N.A. M(1) M(1) Q 1, 2, 3, 4 Logic and Actuation Relays
- 3) Containment S R H N.A. N.A. N.A. N.A. 1, 2, 3 Pressure--liigh-liigh
- c. Purge and Exhaust isolation
- 1) Automatic Actuation N.A. N.A. N.A. N.A. M(I) M(1) Q 1, 2, 3, 4 jg Logic and Actuation u Relays
- 2) Containment Radio- S R H N.A. N.A. N.A. N.A. 1, 2, 3, 4 g
~
logical-liigh
- 3) Safety injection See I ahuye for all InjecUon Surveillance Requirements.
1
\
TA3tE4.3-2(Continued) LNGl :EERED SAIETY fEAlVRE ACillA110ll SYSIIH INSlkilHINI A110N 49 u; 50RVEIFTAEE~REQUIREHENTS u, IRIP ANA10G AClllAl lflG H0 DES CllANNEL 1)EV1Cl HASIER 51 AVE 10R WillCll
. CilANNEL CllANNEL OPERAIlONAL OPERA 110NAL ACIUAIl0N RELAY RELAY SURVEILLANCE FUNCIl0NAL UNIT CilECK CAllllRATION IESI lf51 10Glc IESI lEST IEST IS REQUIRED
- 4. SIEAM LINE ISOLATION I
- a. Manual N.A. N.A. N.A. R N.A. H.A. N.A. I, 2, 3 l
- b. Automatic Actuation N.A. N.A. N.A. N.A. H(1) M(1) Q 1, 2, 3 Logic and Actuation Relays I
- c. Containment Pressure-- S R H H.A. N.A. N.A. N.A. 1, 2, 3 ;
liigh-liigh !
- d. -Sica. Ehu i" Tua Nam S R H N.A. N.A. N.A. N.A. +,4, 3f V !
M
+-
-L4aea - iiiu;. Coinc4 dent /. I w _w4p". 'r e' ". "., A g_ssur,acy.a,w S A-AhhL - Hsyh ,
s
- 1. Iq -tcw-Lew ei S R H -
N.A. -- - - - N . A . ----- N. A . -N.A. - 1 A;
- e_ , & Steam Line S R H N.A. N.A. N.A. N.A. 1,2,3 .
Pressure--Low
- 5. IUR81NE TRIP AND FEEDWATER !
ISOLATION l'
- a. Steam Generator Water S R H N.A. H.A. N.A. H.A. I, 2 Level--liigh-liigh
- b. Automatic Acteation N.A. N.A. N.A. N.A. H(1) H(1) 1, 2 Q
Logic and Actaation Relay
- 6. AUXILIARY IEEDWATER
- a. Manual N.A. N.A. !!. A. R N.A. N.A. H.A. 1, 2, 3
$ b. Automatic Actuation 7;. A. N.A. N.A. N.A. H(1) H(1) Q 1, 2, 3 ;
5 Logic and Actuation Relays
$, c. Steam Generator Water S R H H.A. N.A. N.A. N.A. 1, 2, 3 +
m Level--low-Low 9' G S G
)
IABIE 4.3-2 (Continued) 8T ENGINEERED SAFE 1Y FEATURE ACIUATION SYS)fM INSIRUMENIATION y SURVEllTANCE REQIIIRTHFATS i IRIP l ANAL 0G ACIUAllNG MODES CilANNEL DEVICE MASTER SLAVE FOR WHICH i CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE FUNCTIONAL UNil CilECK CAllBRATION IEST IEST 10GIC IEST 1EST 1EST IS REQUIRED AUXill/.M FEEDWA1ER (Continued) d.
}.- g %g~-2~ N.A.
RE R N.A. R N.A. M.A. N.A. If 2 f 3
- e. Safety injection See 1 above for all Safety Injection Surveillance Requirements
- f. Station Blackout N.A. N.A. N.A. R N.A. N.A. N.A. 1, 2, 3
- g. Trip of Main Feedwater N.A. N.A. N.A R N.A. N.A. N.A. 1, 2 Pumps R
, *-7 AUI(HATIC SWIICH0VER 10
- Y CON AINNENT SUNP 4'Ecl/cul A r/M M
t a. RSWI level - Low
-esineident-With-S R H N.A. N.A. N. A. N.A. I, 2, 3, )
. Conte 4#eent-Sump-teveMS "
N--- -
-N.A. --- N: A. - - N- Ar -- . N . A . - l ,- 2 ,-3 , Hip.Aed-
< Safety injectie. See-1-above-for-all--Safety. Injection-Surveillance Requirements-4i ---Autom4 tic Ac*oatlee N-A. -N,A. LAr -
N.A. ._ M( 1 ) - - -H(1) Q 1, 2, . 3, .A._.
-Logic--and-Aetustion, s Relays-
- 8. LOSS Of POWER
- a. ' 16-kV E -iyist.y Bm
. H.A. -
- R -. - N. A. R -N.A. - N.A. N.A I ; - 2,-3 ;-4s
'-1tndemiaTtage-(Lossml m . -Vol tage)-
u
- 4. b. 0. ;C W E=r;;c:=y s . N.A. R N.A. R. N.A. N.A. H.A. I, 2, 3, 4 m -tindervoltage (Degraded g
Voltage) 5m -
^
i TABLE 4.3-2 (Continued) 'T ENGINEERED SAFETY FEATURE ACTUATION SYSTEN INSTRUMENTATION
] SURVEILLANCE REQUIRERERTS TRIP ANALOG ACTUATING MODES CllANilEL DEVICE MASTER SLAVE FOR WillCil CilANNEL CilANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE FUNCTIONAL UNIT CilECK CALIBRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED ,
- 9. ENGINEERED SAFETY FEATURE !
ACTUATION SYSTEM INTERLOCKS
- a. Pressurizer Pressure, N.A. R H N.A. N.A. N.A. N.A. 1,2,3 P-11 i
- b. Ame, Low T,y , P-12 H.A. R H N.A. N.A. N.A. N.A. 1, 2, 3
- c. Reactor Trip, P-4 N.A. N.A. N.A. R N.A. N.A. N.A. 1,2,3 R.
M
/D. c c.s'TA rdMEN T /TES S uff Cod 7fG S TEM
- a. 'G hr 4 s K tt y ,1_ r .t . 44 N 4. i, ,'. 3. '/
b Tiaa S S A' ,sj S,I g.) MA. N4 ), ~ , 3 , t/ X; o e-- C.#5 O O O
t l TA8LE 4.3-2 (Continued) TA8LENOTATIE (1) Each train shall be tasted at least every 62 days on a STAGGERED TEST BASIS. O l O PSTS 3/4 3- W SEP 15190
INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alarm / trip setpoints within the specified limits. APPLICABILITY: As shown in Table 3.3-6. ACTION:
- a. With a radiation monitoring channel alarm / trip setpoint exceeding the value shown in Table 3.3-6, adjust the setooint to within the limit within 4 hours or declare the channel inoperaole.
- b. With one or more radiation monitoring channels inoperable, take the ACTION shown in Table 3.3-6.
- c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
O SURVEILLANCE REOUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRAT!CN and ANALOG CHANNEL OPERATIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-3. l l l l O y-STS 3/4 3-As . MP 15 ISSI Y7
~
p O 4 l . TABLE 3.3-6 RADIATION HONITORING INSTRUMENTATION m
' MINIMUM CllANNELS APPLICABLE ALARH/ TRIP MEASUREMENT lE
!W INSTRUMENT OPERABLE H0 DES SETPOINT RANGE ACTION m 1. AREA MONITORS P a. Fuel Storage Pool Area
-1
- 104mR/hr Criticality Monitor 1 *
(Fuel Bridge) 1 15 mR/hr 10 R 26-
- b. Containment Area 2 1, 2, 3, & 4 0 8 N/A 10 - 10 rad /hr 28 a'/
- 2. PROCESS HONITORS
- a. Fuel Storage Pool Area Gaseous Activity - '
Ventilation System Isolation 1 ** 1 2 x background 10 - 107cpm -26' 2 7 R *
- b. Control Room Outside Air Intake, Gaseous Activity-Ventilation System
'p,k" Isolation F M 27g g 2 ALL H0 DES 1 2 x background 10 - 107cpm
- c. Containment
- 1. Gaseous Activity 1 (Low Range) a)RCS Leakage Detection 1, 2, 3, & 4 N/A 10 - 10 cp, 7 pg g, ii. Particulate Activity 1 (Low Range) a)RCS Leakage Detection 10 - 107cpm 1, 2, 3, & 4 N/A 26 I' k
Q
- d. Noble Gas Effluent Monitors
- i. Unit Vent 1 0 8 1, 2, 3, & 4 N/A M 10 - 10 rad /hr (gamma) 28}cj m
[ ^ With fuel in the storage pool or building
,o ** With irradiated fuel in the storage pool y
9 e G
1
,f d
TABLE 3.3-6(Continaeg ACTION STATEMENTS ACTION N - With the number of OPERABLE channels less than required by the M Minimum Channels OPERABLE requiremen , perform area surveys of the monitored area with portable mon'toring instrumentation at least once per 24 hours. ACTION 26 - With the number of OPERABLE channels less than. required by the
,2 /,:, Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.7.1.
ACTION 24 - With the number of OPERABLE channels less than required by the 37 Minimum Channels OPERABLE requirement, comply with the ACT20N requirements of Specification 3.9.11. ACTION 2T - With the number of OPERABLE channels less than required by the J8 Minimum Channels OPERABLE requirement, close the affected air intake within one hour; maintain this air intake closed until the channel is restored to OPERABLE status. O ACTION AY - With the number of OPERABLE Channels less than required by the Q/ , Jtf Minimum Channels OPERABLE requirement, restore the inoperable Channel (s) to OPERABLE status within 7 days, or be in at least HOT STANOBY within the next 6 hours and in COLD SHUTDOWN within the subsequent 24 hours.
/ -
T' McGuire - UNIT 1 3/4 3-37 JUN 1981
- ar = ,
o O O g 1ABtE 4.3-3
- g RADIATION HONITORING INSIRUMfNIAll0N SURVLItiANCF RfQUIREMENIS
\ m CilANNLt H0 DES FOR WillCil we CilANNEL Cil3NNEL f uNL fl0NAt sdRVEILLANCL IS fjh CilECK _ C_Al IBliAI10N IESI REQUIRID 3, INS 1RUHFNI b 1. AREA MONITORS
- a. Fue' Storage Pool Area Criticality Honitor S R H ^
(fuel Bridge)
- b. Containment Area S R H 1, 2, 3, & 4
- 2. PROCESS HONITORS
- a. Fuel Storage Pool Area Gaseous Activity -
M Ventilation System [ Isolation S R H ^^ h
- b. Control Room Outside Air Intake, Gaseous Activity-
$)
Ventilation,(System Isolation f h P ,, 2 ' S R H ALL H0 DES
- c. Containment
- i. Gaseous Activity (Low Range) a)RCS Leakage Detection S R H 1, 2, 3, & 4 ii. Particulate Activity (Low Range) a)RCS Leakage Detection S R H 1, 2, 3, & 4
- d. Noble Gas Effluent Monitors e i. Unit Vent S R H 1, 2, 3, & 4 E
^Uith fuel in the storage pool or building m **With irradiated fuel in the storage pool 9
0 9 9
O t
~..
O o . TABLE 3.3-6 , y ( a, b RAOIATION MON 110 RING INSTRUHfHIAll0N MINIMUM
\ INSTRuttENT CilANNELS OPERAHLE APPLICABLE MODES ALARM /IRIP SEIP0lNI MEASUREMENT RANGE ACTION
- 1. AREA I RS
- a. Fuel Storag 001 Area -
4 Critica11t (10 .Ii 10 ) mR/hr
^
- 1. nitor (1) -< 15 mR/hr 25
- 11. Ventilation S em Isolation (1) ^^ (1 2 x backgroun'd) (1 - 10 0) cpm 27
- b. Containment - Purge & . (1 6 (< 2 x background) (1 - 10 6) cpm 28 l Exhaust isolation /
/
4 t c. Control Room Isolation (1) All DES,/ (12 x background) (10 - 10 )mR/hr 29 d d. Containment Area 2 1,);'3& ( ) rad /hr 1-108 rad /hr 30 k\ 2. PROCESS HONITORS
- a. Fuel Storage Pool Area -
Ventilation System Iso ation .
- 1. Gaseous Activity (1) ^^ (< 2 x backgroun41) (1 - 10 53) cpm 21
^^
- ii. Particulate Ac i ity (1) ([2xbackground)N(I-10) cpm 27
- b. Containment
- i. Gaseous clivity a) P Je & Exhaust N solation (1) 6 (< 2 x background)
(1 - 10 ) cpm 28 RCS Leakage Detection (l) 1, 2, 3 & 4 N/A (1 - 10 ) cpii 26
<a i. Particulate Activity C a) Purge & Exhaust
- Isolation (I) 6 (< 2 x background)
- (l - 10 5) CE" 20 m b) RCS Leakage Detection (l) 1, 2, 3 & 4 N/A (1 - 10 ) cpm 26
=
- ^ With fuel in the storage pool or building
^^ With irradiated fuel in the storage pool
i 1AlllE 3.3-6 (Continued) . g RAulATION HONITORING INSTHllHfHIATION HINIMUM
\. CllANNELS APPLICABLE ALARil/lRIP HEASUREHfNT j INSTRUMEHf OPERAlllE HOOLS SLlPolNI _
RANGE ACTION / I PROCESS HONITOR Continued) . 9
- c. Noble Gas E fluent Monitors ,- '
f
- 1. Radwaste Buildi g '
. Exhaust System 1 1, 2, 3 & 4 ti. A. 1-10 uCi/cc 30
'Rg li. Auxiliary Building Exhaust System 1 1, 2, 3 & 4 / N.A. 1-103 uCi/cc 30
(, / Steam Safety Valve ,1:$. K c. iii. Discharge 1/ valve \'1,2,-3'&4 H.A. 1-103 uti/cc 30 e.
\ iv. Atmospheric Steam '/ s I' Oump Valve ./
( Discharge 1/yalve 1, 2, 3 & 4 H.A. 1-10 uCi/cc 30
- v. Shield Buildinu ,
Exhaust Syst # 1 1, 2, 3 & 4 li. A. 1-104 uCi/cc 30 vi. Contairinent Purge & 0 E iaust System 1 1, 2, 3 & 4 H.A. 1-10 uCi/cc 30 vii. Condenser Exhaust System 1 1, 2, 3 & 4 11. A. 1-100 uti/cc 30 ~ C-* Ut O O O
TABLE 3.3-6 (Continued) ACTION STATEMENTS / , N / ACTION 25
/
s - With the number of OPERA 8LE channels less thanAhe Minimum
~ Channels OPERABLE raquirement, perform area,s6rveys of the monitored area with portable monitoring i trumentation at least once per 24 hours.
I \ ' ACTION 26 - With th knumber of OPERABLE channel _ ess than the Minimum Channels OPERABLE requirement, c:mply with the ACTION requirement' of Specification (3A.6.1). ACTION 27 - With the numbe of OPERABLE annels less than the Minimum Channels OPERA 8L requir t, comply with the ACTION require-ments of Specifica on ( .12). ACTION 28 - With the number of OP BLE channels less than the Minimum Channels OPERABLE r ui nt, comply with the ACTION require-ments of Specifica on (3. 9). ACTION 29 - With the number f OPERABLE cttennels less than the Minimum Channels OPE. LE requirement, h thin 1 hour initiate and esintain ope tion of the contro1%om emergency ventilation system in e recirculation mode of eration. ACTION 30 - With th number of OPERABLE Channels les than the Minimum Channe OPERABLE requirement, restore the operable Chann (s) to OPERABLE status within 7 d ys, be in at least HOT TAN 08Y within the next 6 hours, in at leas .0T SHUTDOWN wi in the following 6 hourt and in COLD SHUTOCWN ' ithin the bsequent 24 hours. N
*1 WC E I/ck l
i O esTs $ p si SEP i 51981 l
1ABLE 4.3-3 y RADIA110N HONITORING INSlRllHENIAll0N SURVLill ANCI RIQUIRlHENIS ANA10G CilANNEl H0 DES FOR WillCil CllANNEL CllANNEL OPLRA110NAL SUR'." :'. t ANCE 15
& INSIRUMENT Cll[CK CAllllRAIION W ll SI REQUIRED D
f:, 1. AREA HONITORS
'N a. Fuel Storage Poo grea I'T 1. Criticality HonQor S R H ^
- 11. Ventilation System Isolation p(f' b. Containment - Purge & Exhaust S R H ^^
Q lsolation R H 6
- c. Control Room Isolation S R H All 110 DES e d. Containment Area S R H 1, 2, 3 & 4
- 2. PROCESS HONITORS ,/
- a. fuel Storage Pool Area - Ven- '
tilation System Isolation ,-
- i. Gaseous Activity li. Particulate Activity S -
Rx H ^^ S R \ x H **
- b. Containment ' s,
- i. Gaseous Activity N -
a) Purge & Exhaust \ Isolation S R H 6 b) RCS teakagyu/ etection S It H 1, 2, 3, & 4 li. ParticulatyActivity a) Purgy& Exhaust N isolation S R H 6
$ b),-RCS leakage Detection S R H 1, 2, 3, &,4 o, -, '
m *With,f6el in the storage pool or building. fe **With irradiated fuel in the storage pool. O O O
O O O TABit 4.3-3 (Continued)
l m RADIATION icil10 RING INSTRUMENTATION SURVElilANCE REQUIREMLNIS -
x
\
ANAL 0G x N CilANNEL MODES FOR WillCil CllANNEL CilANNEL Ol' ERAT IONAL SURVEILLANCE IS INSTRilMENT CilECK CAlIBRA110N IESI REQUIRED PROCESS MONITORS (Continued) ./ ! c. Noble Gas Effluent MoniLors '
- i. Radwaste Building ci Exhaust System S
\
R j
.- M 1, 2, 3 & 4 li. Auxiliary Building N, p.
Exhaust System S
/
/li'N, N
M 1, 2, 3 & 4
'b
- g lii. Steam Safety Valve 'x g- Discharge S R 's . M 1, 2, 3 & 4
<g h h w iv. Atmospheric Steam Dump Valve Discharge
\
l
- N S R H \ 1, 2, 3 & 4
- v. Shield Building 'N Exhaust Syste S R M 1, 2, 3 & 4 vi. Contal nt Purge &
Exia l st System .i R M 1, 2, 3 & 4 vil ndenser Exhaust System S R M 1, 2, 3 & 4N,
\
\
e N D, 5
j l INSTRUMENTATION
\
MOVABLE INCORE DETECTORS l LIMITING CONDITION FOR OPERATION 3.3.3.2 The movable incore detection system shall be OPERABLE with:
- a. At least 75% of the detector thimbles,
- b. A minimum of 2 detector thinbles per core quadrant, and
- c. Sufficient movable detectors, drive, and readout equipment to map these thimbles. -
APPLICA8ILITY: When the movable incore detection system is used for:
- a. Recalibration of tas ar. ore neutron flux detection system,
- b. Monitoring the QUADRANT POWER TILT RATIO, or
- c. MeasurementofFh,F(Z)andF q xy ACTICN:
With the movable incore detection system inoperable, do not use the system for the above applicable monitoring or cal _fbration functions. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.3.3.2 The movable incore detection system shall be demonstrated CPERABLE at least once per 24 hours by normalizing each detector output when required for:
- a. Recalibration of the excore neutron flux detection system, or
- b. Monitoring the QUADRANT POWER TILT RATIO, or c.
MeasurementofFh,F(Z),andF,y. q O W-STS ~ 3/4 3.y SEP 151981 J7
O INSTRUMENTATION SEISMIC INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.3 The seismic monitoring instrumentation shown in Table 3.3-7 shall be OPERABLE. APPLICABILITY: At all times. e ACTION: ;0 g ; J . r ; ;=te r g f
- a. With one or more seismic monitoring instruments inoperable for more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 5.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the instru-ment (s) to OPERABLE status.
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
O SURVEILLANCE REQUIREMENTS 4.3.3.3.1 Each of the acove seismic monitoring instruments shall be demon-strated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST operations at the frequencies shown in Table 4.3-4 4.3.3.3.2 Each of the above seismic monitoring instruments actuated during a seismic event greater than or equal to (0.01) g shall be restored to OPERABLE status within 24 hours-- M : C"";;;CL C'd.IS"."TIO : pe. e m d ithic. 5 day; - following the seismic event. Data shall be retrieved from actuatesi instru-ments and analyzed to determine the magnitude of the vibratory ground motion. A Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 10 days describing the magnitude, frequency spectrum and resultant effect upon facility features importalit to safety. O PSTS 3/4 3-FJ R SEP . 51981
~
~~ :_ _ _ _ - - . - . _
i g [r (c TABLE 3.3-7
,t i I'? ^
"7 SEISMIC MONITORING INSTRUMENTATION MINIMUM MEASUREMENT INSTRUMENTS y INSTRUMENTS AND SENSOR LOCATIONS RANGE OPERABLE l \(Triaxial Time-History Accelerographs
/ 1
,' 1 e
- b. .! I
- c. \ / 1
- d. \ ! 1 l 2.TriaxialPeakA\celerographs
\ [
- a. / 1
- b. \ 1
- c. \ 1
- d. N / i g
- e. _
1
- 3. Triaxial Seismic Switches
- a. la
- b. / l*
- c. ! \ 1*
- d. 1*
- 4. Triaxial Respo e-Spectrum Recorders
- a. 1*
- b. 1
- c. 1 1 d. 1 l
e 1 f- * ( Nitn reactor control room indication l W-STS 3/4 3-56 SEP i 51981
TABLE 3.3-7 SEISMIC MONITORING INSTRUMENTATION MINIMUM MEASUREMENT INSTRUMENTS INSTRUMENTS AND SENSOR LOCATIONS RANGE OPERABLE
- 1. Triaxial Time-History Acceleregrapns a.1MIMT 5000 (Remote Sensor A) -2.5g - + 2.5g 1 Containment Base Slab
- o. 19:MT 5010 (Remote Sensor B) -2.5g - + 2.5g 1 Contair. ment Wall Elev. 786'5"
- . iM:MT 5020 (Startar Unit) 0.005 - 0.05g 1 Containment Sase Slao
- 2. Tr1 axial Pe n. Accaiar graphs
- a. 1MIMT $030 Containment Bldg 0-2g 1 Elev. 799' 9 9/16"
- ,'. .er i rQ , c. 1MIMT 5C40 M ry 31dg 0-2g l V Elev. 746' 2 1/2" 1
- c. IMIMT 5050 Auxiliary Bldg 0-2g 1 Elev. 715' 5
- 3. Triaxial Seismic Switches
- a. 1MIMT 5060 Containment Base Slab
- 0.025 - 0.25g 1
- 4. Triaxial Resoonse-Spectrum Recorders
- a. 1MIMT 5070 Containment Base Slab
- 0-2g 1 l b. 1MIMT 5080 Containment Bldg 0-2g 1 Elev. 751' 8 1/4" c.1 MINT 5090 Auxiliary Bldg 0-2g 1 Elev. 750' "Wita reactor control room indication l
l l l 1
'y/
McGUIRE - UNIT 1 3/4 3-j# .5'3 t/Wz r .L
/nsafE
. . - w e "~
O e TABLE 4.3-4 SEISMIC M NITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS CHAHHEL CHANNEL CHANNEL FUNCT'CHAL INSTRUMENTS AND SENSOR LOCATIONS CHECK CALIBRATION TEST
- 1. Triaxial Time-History Accelerographs a.1MIMT 5000 (Remote Sensor A) M" R SA Containment Base Slab
- b. 1MIMT 5010 (Remote Sensor 8) Ma R SA Containmerit Wall Elev. 786'5" c.1MIMT 5020 (Starter Unit) N.A. R SA Containment Base Slab
- 2. Triaxial Peak Accelerographs
- a. 1MIMT 5030 Containment 31dg NA R NA Elev. 799' 9 9/16"
- b. 1MIMT 5040 k Y Y I/"B dg NA R NA Elev. 746' 2 1/2" l s c. 1MIMT SC50 Auxiliary Bldg NA Elev. 716' 6" R NA j]
we
- 3. Triaxial Seismic Switenes
- a. IMIMT 5060 Containment Base Slaba" M R SA 4 friaxial Response-Spectrum Recorders
- a. 1MIMT 5070 Containment Base Slab"" M R EA
- b. 1MIMT 5080 Containment Bldg NA R NA Elev. 751' 8 1/4"
- c. 1MIMT 5090 Auxilidr/ Bldg NA R NA Elev. 750'
Except seismic trigger
**With reactor control room indications.
O O McGUIRE - UNIT 1 3/4 3-il . 6 u vir *:- N
.,r
- s i
TABLE'4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS ANALOG CHANNEL CHANNEL CHANNEL OPERATIONAL INSTRUMENTS AND SENSOR LOCATIONS CHECK CALIBRATION TEST
- 1. Triaxial Time-History Acceleregraphs
- a.
- M* R SA
- b. + ' -
M* R SA
- c. M* R SA
- d. _
M" R SA
- 2. Triaxial Peak Accelerographs
- a. NA R NA
- b. NA R NA
- c. NA R NA
- c. NA R NA
- e. NA R NA
- 3. Triaxial Se:tmic Switches
- a. ** M R SA
- b. **
M R SA
- c. * ** M R SA
- d. ** M R SA
- 4. Triaxial Response-Spectrum Recorders l **
- a. M R SA
- b. NA R SA
- c. NA R SA
,d. NA R SA
- e. NA R SA
- f. NA R SA s
"Except seismic trigger j
**With reactor control room indications. ,- -
(d i C /Fc O W-STS 3/4 3-57 3gp 3 3 ;gg;
INSTRUMENTATION METEOROLOGICAL INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.4 The metsorological monitoring instrumentation channels shown in Table 3.3-8 shall be OPERABLE.
~
APPLICABILITY: At all times. h r_ ACTION:
- a. With one or more required meteorological monitoring channels inoperable for more than 7 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERABLE status.
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicaole.
O SURVEILLANCE REQUIREMENTS 4.3.3.4 Each of the above meteorological monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-5. l O W-STS 3/4 3- W f;-- SEP 151981
- TA8LE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION MINIMUM INSTRLTiENT LOCATION OPERABLE
- 1. WIND SPEED '
, . , :, . ;y .1 ?
- a. 7 .- , Nominal Elev. 7?6 1 in n er.tg .../
- b. -o. .~ , Nominal Elev. ??6 1
- 2. WINO DIRECTION
, , s. ; , , /.- ,./
- a. -r- - ,- , Nominal Elev. 76e 1
- w ,. :,... '
- b. . ,
, Nominal Elev. . 1
- 3. AIR TEMPERATURE - DELTA T a.
m..,,o,..,-
, Nominal Elev.
'# '* - ,'",i 1
6; -
, Nominhl Elev. . . . - _. 1 l
l l l tSTS 3/4 3-55 r& SEP : 51981
l TABLE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL INSTRUMENT CHECX CALIBRATION
- 1. WINO SPEED
- a. Nominal Elev. 7M 0 SA
- b. Nominal Elev. 7 T6 0 SA
- 2. WINO DIRECTION
- a. Nominal Elev. 7 96 0 SA
/
- b. Nominal Elev. *% 0 SA
- 3. AIR TEMPERATURE - DELTA T
- a. Nominal Elev. "T ~ D 0 SA j bqNomirial Elev.- - SA 1
l l l O-3/4 3- W ,.c ,7 SE? 1 E 1931 PSTS l . _ _ _
INSTRUMENTATION REN TE SHUTDOWN INSTRUMENTATION j i I LIMITING CONDITION FOR OPERATION 3.3.3.5 The remote shutdown monitoring instrumentation channels shown in Table 3.3-9 shall be OPERA 8LE with readouts displayed external to the control room. APPLICABILITY: MODES 1, 2, and 3. ACTION:
- a. With the number of OPERABLE remote shutdown monitoring channels less than required by Table 3.3-9, restore the inoperable cnannel(s) to OPERABLE status within 7 days, or be in HOT SHUTDOWN within the next 12 hours.
- b. The provisions of Specification 3.0.4 are not applicable.
!O SURVEILLANCE REOUIREMENTS 4.3.3.5 Each remote shutdown monitoring instrumentation channel shall be demonstrated OPERA 8LE by performance of the CHANNEL CHECX and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-6. i
- O Ld-STS . 3/4 3-pr p f SEP 151981 l
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i l I l TABLE 4.3-6 l i ly
" REMOTE SilUIDOWN MONI10 RING INS 1RUNINIAll0N l , ,
l SEHOlLANCrilE@IRFHCRTS 1 CllANNEL CilANNEL l INSTRUMENT CllECK Call 8 RATION [CPa%ec'6ang(NuclearGux' H Q
.21 r.te r'iard l a tlR andi.l NuefEa r El ux M N.A.
/3 iso 6(ce-Rahge-Nid] ear'Filux- M H.A.
- / 74
- Reactor Trip Breaker Indication H N.A.
/52-Relctor-Chalant lemperature"'lAvera00 M R j'6 [Re{ctorloolan't2Flowiate ~ M R A 2.-7. Pressurizer Pressure M R eT
% 3./. 8. Pressurizer Level M R t/ . - 9. Steam Generator Pressure H R 4' 10. Steam Generator Level M R
.I'll CdntrdY Rod Itosition~ Limit Switcives M R II. lRilR'lOow Rate' H R 1
l'3. [RllR' Yemperfatur.te - M R m (.34. Auxiliary Feedwater Flow Rate M R Q
;7 n.,. s, n .,s : g,, i, 3
. a_. - 1. y 7, , ; e. . ., t'a. , .
e e
-=
INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION , 3.3.3.6 The accident monitoring instrumentation channels shown in Table 3.3-10 l shall be OPERABLE. 1 APPLICABILITY: MODES 1, 2, and 3. ACTION:
- a. With the number of OPERABLE accident monitoring instrumentation cnannels less than the Required Numcer of Channels shown in Table 3.3-10, restore the inoperable channel (s) to OPERA 8LE status within 7 days, or be in at least HOT SHUTDOWN within the next 12 hours,
- b. With the number of OPERABLE accident monitoring instrumentation enannels less than the MINIMUM CHANNELS OPERABLE requirements of Table 3.3-10, restore the inoperable channel (s) to OPERABLE status within 48 hours or be in at least HOT SHUTDOWN within the next 12 hours.
- c. The provisions of Specificatien 3.0.4 are not applicable.
l SURVEILLANCE REQUIREMENTS l i 4.3.3.6 Each accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-7. l l 1 1 O W-STS 3/4 3-jit SEP 151981 G/
-W as--*--hag I
I
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( I I i i l
n f .._.
. . . . . . . .. . . - . _ ~ .-.
DUKE POWER COMPAe!Y a Form 00184 (6 81) Dev./ Station Unit File No. J
, Subject By Date a Sheet No._of Problem No. Checked By Date p 4
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O . TABtC 3.3-10 h ACCIDENI MONIIORING INSTRUMINIA110H
$ MINIMUM REQUIRED j No. OF CilANNELS i INSTRilMENT (Illustrational Only) CllANNELS OPERAlll E 1 1. Containment Pressure 2 1 l %,,, arn/
- 2. 2
] Reactor CoolantJHetlek Temperature - TJNT(WideRange) 1 A7-Rhactbr CopJantQlplet.Teabratuye741gg(Wlue liange) 2 1 ,
- 16. Reactor Coolant Pressure - Wide Range 2 1
*/ 8'. Pressurizer Water Level 2 1 f 9. Steam Line Pressure 2/ steam generator 1/ steam generator s
] 6 4. Steam Generator Water Level - Narrow Range .J.I'/ steam generator 1/ steam generator i'
oh
}4 8,5'2 St'ean Gede(athr$a(er'tavel -LWidg_Habge.- .1/stdam generatpr- -lhteam/gendrator 7 m , Refueling Water Storage Tank Water Level 2 1
,102 Bostic '4cidgask%)ut[o6.Lavek .1 e.I '
8 11. Auxiliary Feedater Flow Rate 2/ steam generator I/ steam generator 9 12'. Re m tor Coolant System Sulicooling Margin Monitor / 2~ O ,1 l // 13. PORV Position Indicator 2/ Valve 1/ Valve
// 14. PokV Glock Valve Position Indicator * /.2/ Valve 1/ Valve hA 15. Safety Valve Position Indicator 2/ Valve 1/ Valve
[/5 14. Containment Water Level (brrod Ra49e) 2 1 h J7.>1ConttiikshWatertleycL(Wide. Range) 2 1
/ '/ 13. In Core Thermocouple, 4/ core quadrant 2/ core quadrant
~; -
g ( s .r e ;,i . i .t "y -
\ p . s , . .. , y t?' '
I
TABLE 4.3-7 sy y ACCIDENT HONITORING INSTRUMENTATION SURVElltANCE REQUIRtHENIS CllANNEL CilANNEL INSTRIMENT (Illustrational Only) CllECK CAL IllRATION
- l. Containment Pressure 7 , ,,,, ./ H R
- 2. Reactor Coolant Dettlet Temperature -jTNT (Wide Range) H R
/3.r'-R'eaqfor-Chola'ht Inl&TemReratug .TdolljdWids. Range) H R ,
.7 & Reactor Coolant Pressure - Wide Range H R 5
4 Pressurizer Water Level H H
.4' Steam Line Pressure H R
[ t' 6 j Steam Generator Water Level - Harrow Range H H t. T 286hstreani G'effecator(Wste:LleVelGWid(R4nge.. H R hk 7 sh Refueling Water Storage Tank Water Level H R
,lDMBar@ Aqid-T49k-Solutiod Ledel' H R 8L Auxiliary feedwater flow Rate H R
- 91. Reactor Coolant System Subcooling Hargin Monitor H R
// f . PORV Position Indicator H R
// 14. PORV Block Valve Position Indicator H R
/4 1 . Sately Valve Position Indicator H R c
o.
/7 ly. Containment Water Level .({arrowJtaiwig) H R
}4 CantilinnentlWarerzLeyele(Wl'de . Range) H R
/9. 18. In Core Thermocouples M R O O O
~
O 'N INSTRUMENTATION N CHLORINE DETECTION SYSTEMS
/
LIMITING CONDITION FOR OPERATION _
'N /
/
3.3.3.7 Two independent chlorine detection systems, with their alarm / trip setpoints adjusted \to actuate at a chlorine concentrati n of less than or equal to 5 ppe, sham be OPERABLE. N APPLICABILITY: ALL MODES / ACTIO.N:
- \s
- a. With one chlorine cietection syptem inoperable, restore the inoperable detection system to OPERABLE / status within 7 days or within tne next 6 hours initiate and maintain operation of the control room emergency ventilation system in the' recirculation mode of coeration.
D. With both cnlorine detectionssystems inoperable, within 1 hour initiate and maintain operation of the control room emergency ventilation systevin tne recirculation mode of operation.
- c. TheprovisionsNfSpecification30)4arenotapplicable.
s
/ 'N N
SURVELLIANCE RE0VIREMENTS
\
4.3.3.7 Each chlorine detection system shall be demonstrated OPkRABLE by perfo nce of a CHANNEL CHECK at least once per 12 hours, an ANALOG CHANNEL s OPERfrTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION at least oned per 18 months. 'g
/ \
'N l
f (/ /Ic7 ( Q W-STS 3/4d-%7 SEP 151981
-w -- - .. _ ,
1 - -
._. -jj /> M r _
O- '
- g. N INSTRUMENTATION ,
FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 7 3.3.3.X As a minimum, the fire detection instrumentation for each fire detection l zone shown in Table 3.3-11 shall be OPERABLE. APPLICABILITY: Whenever equipment protected by the fire detection instrument is required to be OPERABLE. ACTION: With the numoer of OPERABLE fire detection instrument (s) less than the minimum number OPERABLE requirement of Table 3.3-11:
- a. Within 1 hour establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour, unless the instrument (s) is located inside the containment, then inspect the containment at least once per 8 hours or (monitor the containment air temperature at least once per hour at the locations listed in Specification 4.6.1.6).
- b. Restore the inocerable instrument (s) to OPERABLE status within 14 days, or in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the instrument (s) to OPERABLE status.
, c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS Sa v. m l'f 4.3.3.E.1 Eac . ove required fire detection instruments which are ' 'x
^"' accessible during plant oper
- hall be damane9ated4PERABG'ilt least once ,
,N/' per 6 months by performance
- NG DEVICE OPERATIONAL TEST. Fire
')
detectors which accessible during plan . ion shall be demonstrated / OPERA e performance of a TRIP ACTUATING DEVICE m NAL TEST during / e . COLD SHUTOOWN exceeding 24 hours unless performed in the prevTetrs 4_ mon,ths!
'7 4.3.3.3.2 The NFPA Standard 720 supervised circuits supervision associated with the detector alarms of each of the above required fire detection instruments ,
snall be demonstrated OPERABLE at least once per 6 months. 9. g'ff.;' {,",,* -.h ! 7 '",' , 4.3.3.8.3 Thenonsupervisedcircuits,associatedwithdetectoralarms,between[ d: M uct and the control room shall be demonstrated OPERABLE at least once per 31 days. W-STS 3/4 3-fE
- g. y SE? 151991
3p.asr- n ,~ ,g m m UM TATION E ENT 9 ION I N OND RIO R OPERATION
// / ,/ - - /
3.3.3.7, mi um, t e detect,i strumenta 'on # ch re/getec-tion ne o n Tab -11 sha ' PERA8LE. APPLI : n er equi otected t t t ' instru t is r - rdt efERABLE O: / th numbe of R LE f' e ect ins u s) ess han he riium be ORE Er i ment f 6'l e . 1: Wit hour stablis a tre at atro/ t insp ct
/ zone (s) w . e in erpb'le s,,trume (s a eapt 9tice per hpft', unless the s umen s)efs 1 ated in d th on sijnent, thejrinspect the co tains t,a,t'l st'once e hp6rs r,aonit containmen+' 1r temper u efft east on ho4r a the loc i listy '
Speci i (o .6.1.5. /
, ,f
- b. Re to inopera /
einstru/ / to OP RA E st ithin 14 O ment ( ys gr in lieu o y ot ort req 'ied ope 'fiestion E 9,
. 9,4 , repare a ubm' cial Rep t mmis's ' -
ua t' 'd ciff o . wi n the nex day e 'n n, cau e th noperabi y and T't/ st , g th stru t(s) t ERABLE s stus. ' sc e for
. h'e pr si s Spec' cations 3.0 an . 0. 4 a at applicable.
S EIL
/ CE REQUIRE / - /
4.3.3.7.1
& firL Each of the above required seedse detection instruments shall be wpcre,e
[f[ demonstrated OPERABLE at least onceare per e t en FUN ^T'ONAL TEST. Fire detectors which not6 accessible months byduring performance plant opera-of a 0" ANN tion shall be demonstrated OPERABLE by the performance of a 0"."""EL r"MCT!",NAL 7:f'Ir iMy[rg} TEST during each COLD SHUTDOWN exceeding 24 hours unless performed in the i previous six months. Each of the above required fixed temperature / rate of rise detection instruments shall be demonstrated OPERA 8LE as follows:
- a. For nonrestorable spot-type detectors, at least two detectors out of every hundred, or fraction thereof, shall be removed i every five years and sent to a nationally recognized testing f 7%
t
, laboratory for tests. For each failure that occurs on the de- gj tectors removed, two additional detectors shall be removed and i tested. l McGUIRE - UNI 1 g4gT,E__
t I
~
l O SBsVEdLANC17REQUIRJ.MENE (Contintr63) M A -n V // // / / c'/ L/ W LA
- b. For restorable spot-type heat detectors, at least or.e detector on each signal initiating circuit shall be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST. Different detectors shall be selected for each test. Fire detectors which are not accessible during l
plant operation shall be demonstrated OPERABLE by the perfor-mance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTDOWN exceeding 24 hours unless performed in the previous six months. [ h A Code 72 cu ed circuits s* ' associated ala of + e abov ' e ection g[ 'de ' rat at 'I 6m hs. f ed' ween t cal pan
- Sp ren y:jejeahgsu ro, i j mons ed OPERAB at leas' O-O Y
l
=0 1
McGUIRE - UNIT 1 gki-5r M gf
i . INSTRUMENTATION RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm / trip setooints set to
, ensure that tne limits of Specification 3.11.1.1 are not exceedec. The alarm / ,
trio setooints of these enannels shall be determined in accordance with the OFFSITE COSE CALCULATION MAhuAL (OCCM). APPLICABILITY: At all times. MM, ACTION:
- a. With a radioactive liquia effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specification, immediately susoend tne release of radioactive liquid effluents monitored by the affected cnannel or declare the channel inoperable.
- b. With less than the minimum numoer of radioactive liquid effluent monitoring instrumentation channels CPERABLE, take the ACTION shown in Table 3.3-12.
- c. The provisions of Specifications 3.0.3 and 3.0.4 are not aoplicab!e. uncP SURVEILLANCE REOUIREMENTS 4.3.3.8 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SCURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frecuencies shown in Table 4.3-12.
~
snu?4 j McGUIRE - UNIT 1 3/43-g tlA Z 7 2- Gf
~ ' ~ '
_ _ _ - _ _ _ _ --~--
iI ll , ! j O t o p g N 2 i O 0 2 1 / 9 2 L 2 I 3 3 7 3 3 3),3 3 3 3 3 3' w I 3 3 3135 o C l A f n i o t' t
, -' -- u l'
yf f ; i wf d Ar N HLL SE j[- / m- ' i m g i t i O uEB 1 1 1 1 1 I11 1 1 I111 n I l l NA i T I NR n i A NAEl ) ) l ) I l P l t t MCO )
/ A
/1/
i f i M ' t ? s 2 /
.hi U
) n e R
/ v~ I s
/ s a
T S / e N I t /,
/ v 3 /
D('s F l e
- 1 I r G & ,
c N s /-vF )
) d 2,
I R Ygyy
/'
w: c
/
X i u e O T P'- p A [M f i e ) ) q p
. i 1l I 1 ,t /r
, l N
f, T rC ( (t. O a R ,/ <in 3 O ) O 4- e H 1 M T OU g ~ t 3 ( '- e I I N ( ,? s a L T N e /. T A O e e g, in w L B A 1 F I E t J
'L C
I T O A M i L t n e M O I U A WWe n H O L F i L n e e n k i L t n e (% e n ( i t g n a T a G i 'a i c a i n D U s N L R s L o s L i I A ) n I E n l n m U 9 e D t L e t r e t r Q G 4 d I n P d n e d n e I N - n V e M n e t n e t L I F o O m A o m n o m D M C R t S C t I L t k E I E P a a a c V V ( t e D t e w t e o I O i T r N i r o i r l T R e n O T A n T e l n T r C T P n U N U n F U e A N i r S r S i r t 0 E S L n S e R n e E L m n e n I M R o R t E o t C u o t i D U O t i O a L i a I t m i a _ A R T n t T W P t W V n i t W n _ R T IE e a I M a E e n a a _ S NS u l N e A l e D u i l e _ N OA l i OE t S i t l M i t y _ I ME f t MS s t s T f t s b L f n A a E n a N f l n a - YE E e YE W T e W E E a e W d _ TR V TL I V M n V e I d IE l S l E d a l r VF i t VR a O t a R i C t a u IO u q n I n P n n U u n n s T e TF o M e o S q e e o s CN i m CO i O m i A i g m i a AO L n A t C n t E L r n t 0I i 0N n i n M a i n s IT e a I O e S a e e h a e i DA t t DI v U t v E t c t v AN s n AT n O n n T s s n n w RI a o RA o U o o A a i o o o M W C N C N C C R W D C C l . SR SI I f P SE SM T W l OT OR N O mh R . . RE . O . . L . . .. uj G a GT a C a a c O b b F b d m} il n4 iY
. . . . H9 1 2 3 4
- gO g" 'e E2
= _$
%EG J
) ywM
; i i , - i:' j : ,i i
O V TABLE 3.3-12 (Continued) TABLE NOTATION ACTION 30 - With the nuccer of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue for up to 14 days provided that prior to initiating a release:
- a. At least two independent samples are analyzed in accordance with 5pecification 4.11.1.1.1, and
- b. At least two tecnnically qualified members of the Facility Staff independently verify the discharge line valving and (1) The manual portion of the computer input for the release rate calculations performed on tne computer, or (2) The entire release rate calculations if such calculations are performed manually.
Otherwise, suspend release of radioactive effluents via this pathway. ACTION 31 - Q With the number of channels OPERABLE 1ess than required by the Minimum Channels OPERABLE requirement, effluent release via tnis pathway may continue for up to 30 days provided grab samples are analyzed for gross radigactivity (beta or gamma) at a limit of detection of at least 10 7 microcuries/ gram:
- a. At least once per 8 hours when the specific activity of the secondary coolant is greater than 0.01 microcuries/ gram DOSE EQUIVALENT I-131.
- b. At least once per 24 hours when the specific activity of the secondary coolant is less than or equal to 0.01 micro-curies / gram DOSE EQUIVALENT I-131.
ACTION 32 - With the number of channels OPERABLE less than required by the Mimimum Channels OPERABLE requirement, effluent release via this pathway may continue for up to 30 days provided that, at least once per 8 hours, grad sampies are collected and analyzed for gross radioactiv,ity (beta or gamma) at a limit of detection of at least 10 7 microcuries/ml. ACTION 33 - With the number of channels OPERABLE less than required by the Minimum Channels OPERA 8LE requirement, effluent releases via this pathway may continue for up to 30 days provided n the flow rate is estimated at least once per 4 hours (* during actual releases. Pump curves may be used to , estimate flow. i I McGUIRE - UNIT 1 3/4 3-K JUN 1961 VN.77 ^~ 47
O O Q TABLE 4.3-12 IN
@ RADI0 ACTIVE LIQUID EfflUENI MONITORING INSIRUMElll AllON SilRVfill ANCE REQUll:fillllIS I
m lon' / CliANNEL CilANNEL SOURCI CilANNEL -fWN6H6HAL-t-/ 'e 'Nw /
$5 INSTRUMENT CilECK Cill'CK CAllBRATI0ll TEST HG 1.
M- GROSS BETA OR GAMMA RADI0 ACTIVITY MONITORS PROVIDING ALARM AND AU10MATIC TERMINATION IJ of RELEASE
- a. Liquid Radwaste Effluents Line D i> R(3) Q(1)
- b. Containment Ventilation Unit Condensate Line [f/,, rM u-- d D M R(3) Q(1)
{tia,,'f .2 ) P .: y <h @(/) a 2. GROSS BETA OR GAMMA RADI0ACITVITY MONITORS 2 PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC m TERMINATION Of RELEASE
~=
to.i+1)
- a. Conventional Wastewater Treatment Lihe V D M R(3) Q(2)
(tt,o;f z' ) .? 't (,' . ) d(n)
- 3. CONTINUOUS COMPOSITE SAMPLERS AND SAMPLER FLOW MONITOR
- a. Containment Ventilation Uni} Cor densate Line ( p 4" /
- p 1 D N.A. R g (ttn it x) I' A4 A u
- b. Conventional Wastewater Treatment Line D N.A. R Q
- 4. FLOW RATE MEASUREMENT DEVICES
- a. Waste Liquid Effluent Line D(4) it. A. R Q
- b. Containment Ventilation Unit Condensate Line i
.pr u*rl'$ 1 )
( toa i f 2) D(4) N. A. R Q Oty') ii) f 4,
- c. Conventional Wastewater Treatment Line D(4) N.A. R Q
- d. Dischar9e Canal Minimum flow Interlock D(4) N.A. N.A. Q
F . . I U TABLE 4.3-12 (Continued) T_ABLE NOTATION At2Ng , . . 7 U. :v / (1) Thep HANNEL ' ' ::: s/, TEST shall also damonstrate that autcmatic isolation of this pathw&y following conditions and control exist: room alarm annunciation occurs if any cf the
- 1. Instrument indicates measured levels above the alarm / trip setpoint.
- 2. Circuit failure (alarm only).
- 3. Instrument indicates a downscale failure (alarn only).
A,wl:9 :. .v.6l a. I (2) The,1 CHANNEL '...: = N TEST shall also demonstrate that control com alarm annunciation occurs if any of :ne folicwing conditions exist: 1. Instrument indicatas measurec levels above tne Carm sat:oint. i
- 2. Circuit failure.
i 3. Instrument indicates a downscale failure. .. b (3) The initial Channel CALIBRATION snail ce performed using one or more of the reference standards certified by tne National Bureau of Standards or using standards that have been obtained from supplie-s that participate in measurement assurance activities with NiS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CAL!BRATION, sources that have been related to the initial calibration shall be used. (4) CHANNEL CHECK shall consist of verifying indication of flow during periocs of release. CHANNEL CHECX shall be mace at least once per 24 hours on days on which continuous, periodic, or batch releases are made. i
,o.
y Tea I McGUIRE - UNIT 1 3/4 3-56 t/n 2 7 2 - 67
r INSTRUMENTATION RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CCNDITION FOR OPERATION l 3.3.3.9 The radioactive gaseous effluent monitoring instrumentation channels l shown in Table 3.3-13 shall be OPERABLE with their alarm / trip setpoints set to l ensure that the limits of Specification 3.11.2.1 are not exceeded. The alarm / l trip setpoints of these channels shall be determined in accordance with the CDCM. APPLICABILITY: As shown in Table 3.3-13 / d $ - b- - ACTION:
- a. With a radioactive gaseous effluent monitoring instrumentation cnannel alarm / trip setpoint less conservative than required by tne above Scecification, immediately suspend the release of radicactive gaseous effluents monitored oy the affected channel or ceclare tne channel inoperable.
i
- b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation enannels OPERABLE, take the ACTION shown in Table 3. 3-13.
- c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE RECU!REMENTS 4.3.3.9 Each radioactive gaseous effluent monitoring instrumentation chanrel shall be demonstrated CPERA8LE by performance of the CHANNEL CHECX, SOURCE CHECX, CHANNEL CALIBRATION and C"ANNEL I'JNCTICNAL TEST operations at tne l frequencies shown in Table 4.3-13.' '
~
A n'.;. a. w. / c p._ ,. -A ,,u. / l l l l McGUIRE - UNIT 1 3/4 3-52' tMIT 2- 7C
.....-w-w. .sm m +sen *- ** * ~*" " *"
2 TAllt i 3.3-13 a
, 5
- RADIDACIIVE GASE0115 LFf tlif til Hatill0Rilli; lllslialHilllAlloti 1 in
, tilfilHUM CilAf1HL15 gc Ills 1RUMENI OPERAulf APPI l CA111111Y ACII0ft R3 4 hH 1. WASTE GAS Il0LDUP SYSTEM
( I;J y a. Noble Gas Activity Honitor - Providing Alarm and Automatic Termination of Helea:,e
- 35 i k3 1 i
(EHF-50 or Sh&'fft1F*-36)
- b. Effluent System flow Rate Measuring Device 1
^ 36
- 2. WASTE GAS Il0LDUP SYSTEM EXPLOSIVE GAS HON 110 RING SYSTEM i
m a. ilydrogen Monitor 1
^^ 41 D b. Oxygen Monitors 2 ^^ 39 Y
g- 3. CONDENSER EVACUATION SYSTEM (7ft/r,7 s,4s// /) N a. Noble Gas Activity Honitor ': ~ Ri ); 1 ^ 37 (:t s y r . n , u n ,y :1 J -Y- ^t 7
- 4. VENT SYSTEM
{ / Eff,f .N p her / ) a. Noble Gas Activity Honitor('t nf -Msg A ,+- n)
- 1 37 .
j W- 37
- b. lodine Sampler M,/r f) 4 ^
40 14,rw 2> 1 -% W"
- c. Particulate Sampler 4,, * /> ^
40
. u ~ 'r n c/c
- d. Flow Rate MonitorF i t/ e - /) 1
^
36
< si; / ' > l n 56
- e. Sampler flow Rate Monitor (u / / ) 1 ^
36 7 .M. - t u ) ; k- , t. d glefp0}pI',yypPfior tg Q do(c,- I le:f w i 1 l'Ag_ [lat e. uined .by :.icpitig- tau-- NeostireVun'dl,1(1sepMo - tiie , vent._ , l'1 " 7 i i
0erw O O ' l d o I S IAulf 3.3-13 (Continued) RA010AClIVE GASEOUS Eti tufNi MONil0 RING INSIRilMENIATION yC hM MINIMilf t filAllNELS h-' INSTRimENT UPE RAllt E APP 11CABillIY ACTION Y S. CONTAINMENI PURGE SYSTEM
- a. Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release i ^
38
/.f[HF-39 uEMF~ J'/ oror' 367, JCy#ar Wr! *'/ .2 ) .
D '
- 6. AUXILIARY BUILDING VENTILATION SYSIEM t c n f- r , u.uit 1)
- a. Noble Gas Activity Monitor (EHF-41 orj W 1
- 37 (H7f- y,/ c < nhr-sc, *~ - A f 4 37
- 7. FUEL STORAGE AREA VENTILATION SYSTEM g
" a. Noble Gas Activity Monitor [jtMF-42 or 36f, A 1
- 37 Y (arnt- vz u a c , u. y z ) 1 %
D 37
~ \
j t t 4' l
__ l I 1 O V TABLE 3.3-13 (Continued) TABLE NOTATION "At all times.
**0uring aste gas noldup system operation (treatment fcr primary systam offgases).
ACTION 35 - With the number of channels OPERABLE 1ess than reouf red by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment for up .o 14 cays provided that prior to initiating the release:
- a. At least two independent samples of the tank's contents are analyzed, and o.
At least two technically cualified memoers of the Facility Staff independently verify tne discnarge valve lineup anc (1) The manual portion of the computer input for tne release rate calculations performed on the comouter, or (2) O V The entire release rate calculations if such calculations are performed manually. Otherwise, suspend release of radioactive effluents via this pathway. ACTICN 36 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours. ACTION 37 - With the number of channels OPERABLE less tnan required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per 8 hours and these samples are analyzed for gross activity within 24 hours. ACTION 38 - With the number of channels CPERA8LE 1ess than required by the Minimum Channels OPERABLE requirement, immediately suspend VENTING and PURGING of radioactive effluents via this pathway. ACTION 39 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, operation of this system may continue for up to 14 days. With two channels inoperable, be in at least HOT STAND 8Y within 6 hours. ACTION 40 - With the numcer of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue for up to 30 days provided * , V that within 4 hours after the channel has been declared inoperable, 3 samoles are continuously collected with auxiliary sampling equipment as required in Table 4.11-2. I McGUIRE - UNIT 1 3/4 3-pt y uhiZ7~
- f i
i ) TABLE 3.3-13 (Continued) ! TABLE NOTATION ACTION A1 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, suspend oxygen supply to the recombiners. 4 I l McGUIRE - UNIT 1 3/4 3-f,5 vvI 7- z._
.--. ::-== ~ .. _ , _ _
,_ m.,
i d i TABLE 4.3-13 RADIDACTIVE GASEOUS EFFLUENT MONITORING INSlRUMENTATION SURVEILLANCE REQUIREMENTS A ,r.. '. . J
$ CilANid t.. . MODES IN WHICH g
e INSTRUMENT CilANNEL SOURCE CilANNEL fBNeHM. L F SURVEILLANCE CllECK _CilECK CALIBRATION TEST REQUIRED 1 : ] [. 1. WASTE GAS HOLDUP SYSTEM P a. Noble Gas Activity Monitor - ]I Providing Alarm and Automatic 16 # -34 Termination of Release (EHF-50 or M P P R(3) Q(1) *
- 2. ' WASTE GAS If0LDUP SYSTEM EXPLOSIVE GAS MONITORING SYSTEM
- a. Ilydrogen Monitor D N.A. Q(4) M **
{ b. Oxygen Monitor D N.A. Q(5) M **
't' c. Oxygen Monitor (alternate) D N.A. Q(5) M **
q 3. CONDENSER EVACUATION SYSTEM
% '1 EM- 3 fr "*I' '
- a. 'E."." E /f
- Noble Gas Act .? ivity thf- 3) (Moni(tor
, 4r ,;r d O D
M M R(3)
,gf3 s Q(2)
G (2) #
- 4. VENT SYSTEM
(;gmp 7{ , //arit / \
- a. A D M R(3)
- Noble Gas Activity (M,onitor 2 EMP-3( (emf 66)4 *e) P y u~ t'/ gp uQ(2)
(.,) M-~
- b. Iodine Sampler [Nef/*/) W N.A. N. A. N.A. *
(tro * ') W 24 { ,.l )Q ,) <
- c. Particulate Sampler ()," ' - / ) W N.A. N.A.
{ tin f '*) w 34 y ;) N.A. p s, A
- d. Flow Rate Monitori (t/>" V /) D N.A. R Q *
(t/u i + a- ) P p i; /( G -/-
- e. Sampler flow Rate Monitor (e<,,7 /) D N.A. R Q *
(t/~it .x ) P N,) 1 < C
/> .
-r f *)-tdJ ns't'411pd:by' July-17/1981 p
' mea' s tire @n all jnput's tg'.UM[rior.to/ this-T!al_e, '
_ f lotwill '~be_ determined ~by-summjng
'~
'~~' .the. flow, t e.
,r
___ - -__ ~
p O - i l k_
;} .-
5 N Ed S l ABli 4. 3 13- - RAD 10ACIIVE GASt005 Eif1UENI HONIl0RI(1G INSIltullt tiIAi1011 Sill!VE11 LANCE REQUIREMENTS t c: inahy /
}$ .
CilANNEL, g..#'# H0 DES IN WillCH IH CilANNEL
~
SOURCE CllANNEL ft)HC-I-IdNAL SURVEILLANCE INS 1RUHf NI CillCK CllECK CAllBHAII0tl IEST REQUIRED ,
- 5. CONIAINHENI PURGE SYSTEH
- a. Noble Gas Activity Monitor -
Providing Alarm and Automatic Terminat ion of Release i. ,':. ;'3 u, z) (1 EHF-y/ <r .M , H~'t f.) o P R(3) q(1) * (4 EMF - Ty cr .3t. o %H 2 ) P & 6. t' ff3) G(/) AUXILIARY BUILDING VEN11LAT10N SYSTEM
- a. Noble Gas Activity Honitor (EHF-41 Y
5 or iNG 1 EMF- 3 V e b/t /) D H lu3) Q(2) (En,r-y,/ cr at ENF- J& y W4It X ) P b) A(:3) f-{:' ) ~X-7.
. 'f
*4Q IUEL STORAGE AREA VENIILAl10N SYSlLM b a. Noble Gas Activity Monitordi : ;2 c m M (f E/*1f '/'d cr - 3fy ik'Y / ) D tl R(3) Q(2) *
(.2fA/F-y.ztr~ 7(, , Alor & =<.) /2 ^/ N(E ) ([' W or o' s
V TABLE 4.3-13 (Continued) TAB'.E NOTATION
;. s',*, -.mes.
During system offgases). waste gas holdup system operation (tr<satnent for primary 1,,ahf sp~Nw/ (1) The/ CHANNEL M "'q TEST shall also demonstrate'that automatic iso;ation of this pathway and controi room alarm annunciation occurs if any of the following conditions exist: - 1. Instrument indicates measured levels acove tne alarm / trip setpoint.
- 2. Circuit failure (alarm only).
3. Instrument indicates a downscale failure (alarm only). hak.y truahbral (2) ThejCHahNEL .NCT:: M LhTEST snall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:
.3 1.
Instrument indicates measured levels above the alarm setpoint. V) I
- 2. Circuit failure.
3. Instrument indicates a downscale failure. (3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intendeo c:ange of energy and measurement range. For subsequent CHANf'EL CALIBRATION, sources that have been related to the initial calibration shall be used. (4) The CHANNEL CALIBRATION shall include the use of standard gas samples in accordance with the manufacturer's recommer.dations. (5) THE CHANNEL CALIBR,. TION shall include the use of standard gas samples in accordance with the manufacturers recommendations. In accition, a standard gas sample of nominal four volume percent oxygen, balance nitrogen, the oxygenshall be used in the calibration to check linearity of analyzer. f V} McGUIRE - UNIT 1 VN 7 2- 3/4 3-fdr
'7 7 i -1________ . - - _ _ _ _ _ _ _ - -- - - - - - " - - _ _ _ _ _ _ _ _ _ _ . _ _ J
l O TABLE 3.3-11 FIRE DETECTION INSTRUMENTS INSTRUMENT LOCATION (Illustrative **) MINIMUM INSTRUMENTS OPERABLE
- HEAT FLAME SMOKE
- 1. Containment Zone 1 Elevation Zone 2 Elevation
- 2. Control Room a
- 3. Cable Spreading Zone 1 Elevation
,.4i j6, g Zone 2 Elevation . . gf 6 '
- 4. Computer Room b ut(
- 5. Switchgear Room
- 6. Remote Shutdown Panels Station Battery Rooms O 7.
Zone 1 Elevation Zone 2 Elevation
- 8. Turbine Zone 1 Elevation Zone 2 Elevation
- 9. Diesel Generator Zone 1 Elevation Zone 2 Elevation
- 10. Diesel Fuel Storage -
- 11. Safety Related Pumps Zone 1 Elevation Zone 2 Elevation
- 12. Fuel Storage Zone 1 Elevation Zone 2 Elevation "The fire oetection instruments located within the Containment are not required to be OPERABLE during the performance of Type A Containment Leakage Rate Tests.
"" List all detectors in areas required to insure the OPERABILITY of Safety reisted equipment and indicate instruments which automatically actuate fire suppression systems.
J// V59' y-STS SE? . 51981
, Y
INSTRUMENTATION l LOOSE-PART DETECTION INSTRUMENTATICN LIMITING CONDITION FOR OPERATION
/0 3.3.3.S The loose part detection system shall be OPERABLE.
APPLICABILITY: MODES 1 and 2 ACITON:
- a. With one or more loose part detection system channels inoperable for more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and tne plans for restoring the enannel(s) to OPERABLE status.
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIRENENTS
/4 4.3.3.8 Each channel of the loose part detection systems shall be demonstrated l OPERABLE by performance of:
- a. A CHANNEL CHECK at least once per 24 hours, ACAMAw. C.mt;;;LL QPtMAr1CNAt=T[5T -L id:t--once p, 3L Cys,
--t
$. A CHANNEL CALIBRATION at least once per 18 months.
i l l 9 M-STS 3/4 3- zggj l gy3
O ' INSTRUMENTATION 3/4.3.4 TUR8INE OVERSPEED PROTECTION . LIMITING CONDITION 80R OPERATION 3.3.4 At least one turbine overspeed protection system shall be OPERABLE. APPICA8ILITY: MODES 1, 2, and 3. ACTION:
- a. With one stop valve or one governor valve per high pressure turoine steam lead inoperable and/or with one reheat stop valve or one reheat intercept valve per low pressure turbine steam lead inoperable, restore the inoperable valve (s) to OPERABLE status within 72 hours, or close at least one valve in the affected steam lead (s) or isolate the turbine from the steam supply within the next 6 hours.
- b. With the above required turbine overspeed protection system otherwise inoperable, within 6 hours isolate the turbine from the steam supply.
O SURVEILLANCE REQUIREMENTS 4.3.4.1 The provisions of Specification 4.0.4 are not applicable. 4.3.4.2 The above required turbine overspeed protection system shall be demonstrated OPERABLE:
- a. At least once per 7 days by cycling each of the following valves through at least one complete cycle from the running position.
- 1. (Four) high pressure turbine stop valves.
- 2. .(Four) high pressure turbine governor valves.
so n
- 3. (Sour) low pressure turbine reheat stop valves.
rix
- 4. -(.Eeus) low pressure turbine reheat intercept valves,
- b. At least once per 31 days by direct observation of the movement of each of the above valves through one complete cycle frJm the running position.
- c. At least once per 18 months by performance of a CHANNEL CALIBRATION on the turbine overspeed protection systems.
- d. At least once per 40 months by disassembling at least one of each of O the above valves and performing a visual and surface inspection of valve seats, disks and stems and verifying no unacceptable flaws or corrosion.
hbSTS 3/4 3-JT NOV 2 '991 71 bmpuuumu u up uuuuu
O 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS _AND COOLANT CIRCULATION STARTUP AND POWER OPERATION i LIMITING CONDITION FOR OPERATION i 3.4.1.1 All reactor coolant loops shall be in operation. APPLICA8ILITY: MODES 1 and 2.* ACTION: With less than the above required reactor coolant loops in operation, be in at least HOT STANOBY within i hour. O SURVEILLANCE REQUIREMENT 4.4.1.1 The above required reactor coolant loops shall be verified to be in operation and circulating reactor coolant at least once per 12 hours. l "See special Test Exception 3.10.4 PSTS 3/4 4-1 gay 151980 _ _ _ , . ,,_y_ - , . _ -
REACTOR COOLANT SYSTEM HOT STANDBY LIMITING CCNDITION FOR OPERATION _ 3.4.1.2 a. At least two of the Reactor Coolant loops listed belos shall be OPERABLE:
- 1. Reactor Coolant Loop (A) and its associated steam generator and Reactor Coolant pump,
- 2. Reactor Coolant Loop (B) and its associated steam generator and Reactor Coolant pump,
- 3. Reactor Coolant Loop (C) and its associated steam generator and Reactor Coolant pump, 4 Reactor Coolant Loop (D) and its associatec steam generator and Reactor Coolant pump.
- b. At least one of the above Reactor Coolant loops shall be in operation."
APPLICABILITY: MODE 3 ACTION:
- a. With less than the above required Reactor Coolant loops OPERABLE, restore the required locos to OPERABLE status within 72 hours or be in HOT SHUTDOWN within the next 12 hours.
- b. With no Reactor Coolant loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required Reactor Coolant loop to operation.
SURVEILLANCE REOUIREMENTS 4.4.1.2.1 At least the above required Reactor Coolant pumps, if not in operation, shall be determined to be OPERABLE once per 7 days by verifying correct breaker alignments and indicated power availability. 4.4.1.2.2 The required steam generators shall be determined OPERABLE by verifying secondary side water level to be greater than or equal to (+FO at least once > per 12 hours. /2 % 4.4.1.2.3 At least one Reactor Coolant loop shall be verified to be in operation and circulating reactor coolant at least once per 12 hours.
^All Reactor Coolant pumps may be de-energized for up to 1 hour provided (1) no operations are permitted that would cause dilution of the reactor coolant system boron concentration, and (2) core outlet temperature is maintained at least 10*F below saturation temperature.
W-STS
- 3/4 4-2 NOV.1.5 1E80 1
O REACTOR COOLANT SYSTEM HOT SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.1.3 a. At least two of the Reactor Coolant and/or residual heat removal (RHR) loops listed below shall be OPERABLE:
- 1. Reactor Coolant Loop (A) cnd its associated steam generator and reactor coolant pump,"
- 2. Reactor Coolant Loop (B) and its associated steam generator and reactor coolant pump,"
3 .' Reactor Coolant Loop (C) and its associated steam generator and reactor coolant pump,"
- 4. Reactor Coolant Loop (D) and its associated steam generator and reactor coolant pump,*
- 5. Residual Heat Removal Loop (A),
- 6. Residual Heat Removal Loop (B).
O b. At least one of the above Reactor Coolant and/or RHR loops shall be in operation."* APPLICABILITY: MODE 4. ACTION:
- a. With less than the above required Reactor Coolant and/or RHR loops OPERABLE, immediately initiate corrective action to return the required loops to OPERABLE status as soon as possible; if the remaining OPERABLE loop is an RHR loop, be in COLD SHUT 00WN within 24 hours.
- b. With no Reactor Coolant or RHR 1o00 in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required coolant loop to operation.
30 "AReactorCoolantpumpshallnotbestartedwithoneormoreof/tneReactor Coolant System cold leg temperatures less than or equal to (24 )*F unless
- 1) the pressuri:er water volume is less than N ec cubic feet or 2) the secondary water temperature of each steam generator is less than to F above each of the Reactor Coolant System cold leg temperatures.
l **All Reactor Coolant pumps and residual heat removal pumps may be de-energized for up to I hour provided 1) no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration, and 2) core outlet temperature is maintained at least 10*F below saturation temperature. W-STS 3/4.4-3 l JUL 2 7 581
~
l l REACTOR CCOLANT SYSTEM SURVEILLANCE REOUIRE.uENTS 4.4.1.3.1 The required Reactor Coolant pump (s), if not in ooeration, shall be determined to be CPERABLE once per 7 days by verifying correct breaker alignments and indicated power availaoflity. 4.4.1.3.2 The required steam generator (s) shall be determined OPERABLE cy verifying secondary side water level to be greater than or equal to (W)*. at least once per 12 hours. /2 4.4.1.3.3 At least one Reactor Coolant or RHR loco shall be verified to be in operation and circulating reactor coolant at least onqe oer 12 hours. O i l 1 l O
'f- STS 3/4 4-4 N0i 2 01980
O REACTOR COOLANT SYSTEM COLD SHUTOOWN LIMITING CONDITION FOR OPERATION
- 3. 4.1. 4 Two# residual heat removal (RHR) loops shall be OPERABLE
- and at least one RHR loop shall be in operation **.
APPLICABILITY: MODE SN. yg: A
- a. With less than the above required RHR/ Reactor Coolant locos CPERABLE, immediately initiate corrective action to return the required RHR/ Reactor Coolant loops to OPERABLE status as soon as possible.
- c. With no RHR loop in operation, suspend all operations involving a reduction in boron concentratis -f the Reactor Coolant System and immediately initiate correctve aaton to return the required RHR loop to operation.
h' v SURVEILLANCE REQUIREMENTS
- 4. 4.1. 4 At least one RHR loop shall be determined to be in operation and circulating reactor coolant at least once per 12 hours.
#0ne RNR loop may De inoperable up to 2 hours for surveillance testing provided the other RHR loop is OPERABLE and in operation. Four filled Reactor Coolant loops with at least two steam generators having levels greater than or equal to 12 percent may be substituted for one RHR loop.
# A Reactor Coolant pump shall not be started with one or more of the Reactor Coolant System cold leg temperatures less than or equal to 300*F unless
- 1) the pewssurizer water volume is less than 1600 cubic feet or 2) the secondary water temperature of each steam oenerator is less than 50*F above each of the Reactor Coolant System cold leg temperatures.
"The normal or emergency power source may be inoperable.
**The RHR pump may be de-energized for up to 1 hour provided 1) no operations are permitted that would cause dilution of the reactor coolant system boron concentration, and 2) core outlet temperature is maintained at least 10*F below saturation temperature.
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McGUIRE - UNIT 1 3/4 4-5
l
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g(& O N REACTOR COOLANT SYSTEM COLD SHUTDOWN - LOOPS FILLED LIMITING CONDITION FOR OPERATION /
/ M 3.4.1.4.1 At least one resicual heat removal (RHR) loop snal be OPERABLE and l
in operation *, and either: l a. One additional,RHR loop snal) be OPERABLE #, or
\
- b. The seconoary is'de water level of at least two steam generators shall be g. eater than (W)%. /
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APPLICABILITY: MODE 5 witn Reactor Coolant loops 11ed , ACTION:
- a. With less than the abovesrequired lo/ ops OPERABLE or with less than therequiredsteamgeneratorlevef,immediatelyinitiatecorrective action to return the required loops to OPERABLE status or to restore the required level as soon as possible.
- b. k With no RHR loop in operation, suspend all operations involving a reduction in boron concentratioriNof the Reactor Coolant System and O immediately initiate corre'tive loop to operation. '
c a' tion to return the required RHR
, SURVEILLANCE REQUIREMENTS /
I
/
4.4.1.4.1.1 The required R loop shall be demonstr ed OPERABLE pursuant to Specification 4.0.5. 4.4.1.4.1.2 The secondary side water level of at least wo steam generators when requi 'ed shall be determined to be within limits.at least once per 12 hours. 4.4.1.4.1.3 At lpest one RHR loop shall be determined to be in operation and circulating re or coolant at least once per 12 hours. l t One RHR 1 op may be inoperable for up to 2 hours for surveilla ce testing i provide the other RHR loop is OPERABLE and in operation. 3 A Re torCoolantpumpshallnotbestartedwithoneormoreof/th Reactor , Coo nt System cold leg temperatures less than or equal to (4M)*F\nless l 1) he pressurizer water volume is less than /6cc cubic feet or 2) the ! sycondary water temperature of each steam generator is less than Ic '
- F fboveeachoftneReactorCoolantSystemcoldlegtemperatures.
**The RHR pump may be de-energi:ed for up to 1 hour provided 1) no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration, and 2) core outlet temperature is maintained at least 10*F below sn.-4 ration temperature.
M ;;, . , , s . 7, e , =< . o z . . o w . c.- va e s' r : -
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W-STS ;$f 465' JUL 2 71981
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1 _ _l_ _ _ . . . . - - . -- -
lp((G EACTOR COOLANT SYSTEM COLD HUTD0%N - LOOPS NOT FILLED LIMITING C ITION FOR OPERATION N 3.4.1.4.2 Two resf< ual heat removal least one RHR loop s{ hall be in oper:: tion.* (RHR) loops shall be OPzRABLE APPLICABILITY: MODE 5 w Reactor Coolant loops not f led. ACTION:
- a. With less than the abo e required loops PERABLE, inmediately initiate corrective action to rebJrn the requir loops to OPERABLE status as soon as possible.
- b. With no RHR loop in operatio suspend all operations involving a reduction in boron concentratibg/of the Reactor Coolant System and 3 insediately initiate correctiv( ction to return the required RHR i loop to operation.
SURVEILLANCE REOUIREMENTS 4.4.1.4.2.1 The required RHR oops shall be demonst ted OPERABLE pursuant to Specification 4.0.5. 4.4.1.4.2.2 At least on R loop shall be determin(d be in operation and circulating reactor coo nt at least once per 12 hours. OneRHRloo[saybeinoperableforupto2hoursforsurveill e testing providad t e other RHR loop is OPERABLE and in operation. A ' ' " ' ' ~ einew . iv.. a s o ,-e e i,w y .se , ,, S/.--- m .
- The RH pump may be de-energized for up to I hour provided 1) no erations are p itted that would cause dilution of the Reactor Coolant Systh boron cons ntration, and 2) core outlet temperature is maintained at leasty0*F
/ bow saturation temperature. \
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l O
-w-STS g/4 W NOV4- 1981
)
REACTOR COOLANT SYSTEM ISOLAYED. LOOP (OPTIONAL) .- N '
/
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LIMITING CDMDITION FOR OPERATION / 3.4.1.5 The baron' concentration of an isolated loop shall be maintained greater than or equal \to the boron concentration of the' operating soops. APPLICA8ILITY: MODESlh2,3,4,and5.
'N /
[ ACTION: N, j-
/
With the requirements of the above specification not satisfied, do not .open the isolated loop's stop valves; either' increase the boron concentration of the isolated loop to within the limits within 4 hours or be in at least HOT STANDBY within the next 6 hours with the unisolated portion of the RCS borated to a SHlITDOWN MARGIN equivalent,to at least 1% delta k/k at 200*F.
/
/ '
O
/
l SURVEILLANCE REQUIREMENTS
/ .
4.4.1.5/ The baron cancentration of an isolated loop shall be\ determined to be , greater than or equal to the boron concentration of the operati'ng loops at least once per 24 hours and within 30 minutes prior to opening either the hot leg or cold leg stop valves of an isolated loop. N
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i / pjy' ' , d- t/h / t-O l y-STS 3/f4W POV 2 1981 ? ___ . - - _ _ . - . , . , . -. , c- w
REACTOR COOLANT SYSTEM ISOLATED LOOP STARTUP (OPTIONAL) LIMITING CONDITION FOR OPERATION \ 3.4.1.6 A reactor coolant loop shall remain isolated until: x a. The isolated loop has been operating on a recirculation flow of N gpm for at least_.90 minutes and the greater than or equal totemperatureatthecoldlWoftheisolatedloopiswithin20
\ N the highest cold leg temperature of the operating loops.
- b. 'T'he reactor'is subcritical by at least 1 percent delta k/k.
APPLICA8ILIT(: ALL MODES. ACTION: With the requirements of the above specification not satisfied, suspend startup of the isolated loop. SURVEILLANCE REOUIREMENTS
'N 4.4.1.6.1 The-isolated loop cold leg temperature shall besdetermined to be within 20*F,of the highest cold leg temperature of the opersti.ng loops within 30 minutes / prior to opening the cold leg stop valve. N
/ \
- 4. 4.1. E.'2 The reactor shall be determined to be subcritical by at' least 1 percent delta k/k within 30 minutes prior to opening the cold leg stop valve.
/
j v l ff /, hohn 9 W-STS j{t45-8 4;'// 2 1931
a REACTOR COOLANT SYSTEM 3/4.4.2 SAFETY VALVES SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.2.1 A minimum of one pressurizer code safety valve shall be OPERABLE with a lift setting of 2485 PSIG ! 1%." APPLICABILITY: MODES 4 and 5. ACTION: With ne pressuri:er ecce safety valve OPERASLE, ir. mediately suscend all coerations involving positive reactivity enanges anc olace an OPERABLE residual neat removal loop into coeration in :ne snutoown cooling mode. SURVEILLANCE REQUIREMENTS 4.4.2.1 No additional Surveillance Requirements other than those required by Soecification 4.0.5. l 1 i l t i
"The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.
- a w*t W-STS' 3/4 4-B'es" 6 - -
[.______ _ _ _ _ . _ _ __ _ _ _ REACTOR COOLANT SYSTEM OPERATING LIMITING CONDITION FOR OPERATION l 3.4.2.2 All pressurizer code safety valves shall be OPERABLE with a lift setting of 2485 PSIG 1%.* APPLICABILITY: MODES 1, 2, and 3. l ACTION: l With one pressurizer code safety valve inoperable, either restore the l inoperable valve to OPERABLE status within 15 minutes or be in at least HOT ' STANDBY within 6 hours and in at least HOT SHUTOOWN within the following 6 hours. 1 SURVE!LLANCE REOUIREMENTS 4 4.4.2.2 No additional Surveillance Requirements other than those required by ! Specification 4.0.5. l "The lift setting pressure shall correspond to ambient conditions of the valve l at nominal operating temperature and pressure. l O
' -STS f 3/4 4- gj 7
^
1 . . _ i i O REACTOR COOLANT SYSTEM 3/4.4.3 PRESSURIZER LIMITING CONDITION FOR OPERATION
- ;. ., <. . -1 -
3.4.3 The, pressurizer shal equal to (4 cubic feet,)1and beatOPERABLE with least two groups a water volume of pressurizer heaters of less than or each having a capacity of at least (150) kw. APPLICABILITY: MODES 1, 2, and 3. ACTION:
- a. With one group of pressurizer heaters incoerable, restore at least two groups to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours and in HOT SHUTDChN within the folicwing 6 hours,
- b. With the pressurizer otherwise inoperable, be in at least HOT STAND 3Y with the reactor trip breakers open within 5 hours and in HOT SHUTDOWN within the following 6 hours.
O SURVEILLANCE REOUIREMENTS 4.4.3.1 The pressurizer water volume shall be determined to be within its i limit at least once per 12 hours. 4.4.3.2 The capacity of each of the above required groups of pressurizer heaters shall be verified by measuring circuit current at least once per 92 days. 4.4.3.3 The emergency power supply for the pressurizer heaters shall be demonstrated OPERABLE at least once per 18 months by manually transferring power from the normal to the emergency power supply and energizing the heaters. l O l NOV 2 1981 PSTS 3/4 4- W g g -w- w y- g,,m ,- -,. ,_-~, .-w,,-
i i REACTOR CCOLANT SYSTEM 3/4.4.4 RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.4 All power-coerated relief valves (PORVs) and their associated block valves shall be OPERABLE. APplICA8Ii.ITY: MODES 1, 2, and 3. ACTION:
- a. With one or more PORV(s) inoperable, within 1 hour either restore the PORV(s) to OPERABLE status or close the associated block valve (s) and remove power from the block valve (s); otherwise, be in at least HOT STANDBY within the next 6 hours and in COLD SFUTDOWN within the following 30 hours.
- b. With one or more block valve (s) inoperable, within 1 hour either restore the block valve (s) to OPERABLE status or close the block valve (s) and remove power from the block valve (s); otherwise, be in at least HOT STANOBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
- c. The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS 4.4.4.1 In addition to the requirements of Specification 4.0.S, each PORV shall be demonstrated OPERABLE at least once per 18 months by:
- a. Performance of a CHANNEL CALIBRATION, and
- b. Operating the valve through one complete cycle of full travel.
1 4.4.4.2 Each block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel unless the block valve is closed with power /emoved in order to meet the requirements l of Specification 3.4.4.a. 1 i 4.4.4.3 The emergency power. supply for the PORVs and block valves shall be i demonstrated OPERABLE at laast once per 18 months by: i Manually , transferring motive and control power from the normal to a. the emergency power supply, and i
- b. Operating the valves through a complete cycle of full travel. .
E-5T5 3/4 4-Jr H- c/ NOV 2 ISSI
O REACTOR COOLANT SYSTEM 3/4.4.5 STEAM GENERATORS LIMITING CONDITION FOR OPERATION 4 3.4.5 Each steam generator shall be OPERABLE. l l APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: With one or more steam generators inoperable, restore tne inoperable generator (s) to OPERABLE status prior to increasing T,yg above 200'F. SURVEILLANCE REOUIREMENTS 4.4.5.0 Eacn steam gene.ator shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5. 4.4.5.1 Steam Generator Samole Selection and Inscection - Each steam generator shall be ceterminec OPERABLE curing snutcown Dy selecting and inspecting at least the minimum number of steam generators specified in Table 4.4-1. 4.4.5.2 Steam Generator Tube Samole Selection and Inspection - The steam generator tune minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table 4.4-2. The inservice inspection of steam generator tubes shall be performed at the fre-quencies specified in Specification 4.4.5.3 and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 4.4.5.4. The tubes selected for each inservice inspection shall include at least 3% of the , total number of tubes in all steam generators; the tubes selected for these inspections shall be selected on a random basis except:
- a. Where experience in similar plants with similar water chemistry indicates critical areas to be inspected, then at least 50% of the tubes inspected shall be from these critical areas.
- b. The first sample of tubes selected for each inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:
O l W-STS
~
3/4 4-Pf
./,L M
i l REACTOR COOLANT SYSTEM SURVEILLANCE REOUIREMENTS (Continued)
- 1. All nonplugged tubes that previously had detectable wall penetrations (greater than 20%).
- 2. Tubes in those areas where experience has indicated potential problems.
- 3. A tube inspection (pursuant to Specification 4.4.5.4.a.8) shall be performed on each selected tube. If any selected tube does not permit the passage of the eddy current probe for a tube inspection, this shall be recorced and an adjacent tube shall be selected and subjected to a tube inspection.
- c. The tubes selected as the second and third samples (if required by Table 4.4-2) during each inservice inspection may be subjectad to a partial tube inspection provided:
- 1. The tunes selected for these samples include the tubes from those areas of the tube sheet array where tubes with imperfections were previously found.
- 2. The inspections include those portions of the tuces wnere imperfections were previously found.
The results of each sample inspection shall be classified into one of the following three categories: Category Insoection Results C-1 Less than S of the total tubes inspected are degraded tubes and none of the inspected tubes are defective. C-2 One or more tubes, but not more than 1% of the total tubes inspected are defective, or between 5% and 10% of the total tubes inspected are degraded tubes. C-3 More than 10% of the total tubes inspected are degraded tubet or more than 1% of the inspected tubes are defective. Note: In all inspections, previously degraded tubes must exhibit significant (greater than 10%) further wall penetrations to be included in the above percentage calculations. O W-STS 3/4 4 ,14 NOV 2 '991 g ,, f
(D ' V REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.3 Insoection Freouencies - The above required inservice inspections of steam generator tuces snail De performed at the following frequencies:
- a. The first inservice inspection shall be performed after 6 Effective Full Power Months but within 24 calendar months of initial criticality.
Subsequent inservice inspections shall be performed at intervals of not less than 12 nor more than 24 calendar months after the previous inspection. If two consecutive inspections following service under AVT conditions, not including the preservice inspection, result in all inspection results falling into the C-1 category or if two consecutive inspections demonstrate that previously observed degra-dation has not continued and no additional degradation has occurred, the inspection interval may be extended to a maximum of once per 40 months.
- b. If tne results of the inservice inspection of a steam generator
, conducted in accordance with Table 4.4-2 at 40-month intervals fall in Category C-3, the inspection frequency shall be increased to at least once per 20 months. The increase in inspection frequency shall apply until the subsequent inspections satisfy the criteria of O. Specification 4.4.5.3.a; the interval may then be extended to a maximum of once per 40 months. l l c. Additional, unscheduled inservice inspections shall be performed on each steam generator in accordance with the first sample inspection specified in Table 4.4-2 during the shutdown subsequent to any of the following conditions:
- 1. Primary-to-secondary tubes leaks (not including leaks originating from tube-to-tube sheet welds) in excess of the limits of l Specification 3.4.6.2.
- 2. A seismic occurrence greater than the Operating Basis Earthquake.
- 3. A loss-of-coolant accident requiring actuation of the engineered safeguards.
- 4. A main steam line or feedwater line break.
l l r NOV 2 i931 W-STS 3/4 4-A6
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REACTOR CCOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.4 Acceotance Criteria
- a. As used in this Specification:
- 1. Imoerfection means an exception to the dimensions, finish or contour of a tube frcm that required by fabrication drawings or specifications. Eddy-current testing indications below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections.
- 2. Decradation means a service-induced cracking, wastage, wear or l generai corrosion occurring on either inside or outside of a tube.
- 3. Degraded Tube means a tube containing imperfections greatu tnan or equal to 20% of the ncminal wall thickness caused by degradation.
1 % Dearadation means the percentage of the tube wall thickness affactea or removed by degradation.
- 5. Defect means an imperfection of sucn severity that it exceeds tne plugging limit. A tube containing a defect is defective.
- 6. Pluooina Limit means the imperfection depth at or beyond which tne tuce snall be removed from service and is equal to (40)%*
of the nominal tube wall thickness.
- 7. Unserviceable describes the condition of a tube if it leaks or contains a cefect large enough to affect its structural integ-rity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break as specified in 4.4.5.3.c, above.
- 8. Tebe Insoection means an inspection of the steam generator tube Trom tne point of entry (hot leg side) completely around the U-bend to the top support of the cold leg.
l l l "Value to ce cetermined in accordance with the recommendations of Regulatory j Guide 1.121, August 1976. l NOV 2 1931 i PSTS 3/4 4-Wg / 3 l
l o d REACTOR COOLANT SYSTEM i
- SURVEILLANCE REOUIREMENTS (Continued) 1 i
- 9. Preservice Insoection means an inspection of the full length of eacn tuce in each steam generator performed by eddy current techniques prior to service to establish a baseline condition of the tuning. This inspection shall be performed after the field hydrostatic test and prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections.
- b. The steam generator shall be determined OPERABLE after completing the corresponding actions (plug all tubes exceeding the plugging limit and all tubes containing through-wall cracks) required by Table 4.4-2.
4.4.5.5 Reoorts
- a. Witnin 15 days following the completion of each inservice inspection of steam generator tubes, the number of tubes plugged in each steam generator shall be reported to the Ccmmission in a Special Reoort l pursuant to Specification 6.9.2.
lO l l
- b. The complete results of the steam generator tube inservice inspection shall be suositted to the Commission in a Specia Report pursuant to l
Specification 6.9.2 within'12 montns following the completion of the inspection. This Special Report shall include:
- 1. Number and extent of tubes inspected.
- 2. Location and percent of wall-thickness penetration for each indication of an imperfection.
- 3. Identification of tubes plugged.
- c. Results of steam generator tube inspections which fall into Category C-3 and require prompt notification of the Commission shall be reported pursuant to Specificati.on 6.9.1 prior to resumption of plant operation. The written followup of this report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.
l jf-STS 3/44-)T NOV 2 i331
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- u o-i c u z3 - _3 3_ 33= u jg gy- pc w < ~ = 3 3 g-w 9 _- 2 S i ==
>$ .52 w - -
w m 2 & .s.
. * - ==-u
_a u. e - .2 I-d =c -.= m Q z
= =
I"
- 2. 1 ,j u= = 5 ,g I 52 S[
v= 2-3 y * *2 e o en ra m 3-
"i =3
~
2 C 3 2 * ^. = = - 3 Q 2 w c 2 ' =a 2-% r 3 , =' 3 == 5 v s: : == 3 u a .= E.5 ? - U .9 - 35 3 w Eh .! i a r .5 !. a ;! - g_ z z -
=52= -=-=
-v i = =.,2 A -
s-1 r >ss" an = s
= = co*sy 2-
=
~=
a _3
=
.2
- . d =3oIs = 'i g, a s
8. 5 n li t il E- c- Ei 3 .g = W = s.=, .. a,, =a = .,_=-
~
]f-O '
d = .= I y,. -= = 2 E & $ *Od'2 au C5
.w s,
+. = g2_,
a = . e d
.2
=
.e
=
J 1
.. iz = =- i=s
= .a oy a .I; -= *a 3 3*s o e-
.3 D
s o
-a e _
2=*1 O us Ms_24 9x -1.3N.
> .=
=~ O ] g ;iJ I * -
5 = -
~
m
- 6 .9 y 2
- c. Z u. m g 0
l W-STS
, 3/4 4- g --
!;'j! 2 1981 44- h .
1 i l l
% i l
'T l h TABLE 4.4-2 l
l STEAM GENEHATOR TUBE INSPECTION IST SAMPLE INSPECTION 2ND 3 AMPLE INSPECTION 3HD SAMPLE INSPECTION Sample Slee Result Action Required flesult Action Heiguired flesult Action Recauired A minimum of C-1 None N/A N/A g, N/A N/A S Tubes per S. G. C-2 Plug defective tubes C-l None N/A N/A and inspect additional Plug defective tubes C-1 None 2S tubes in this S. G. C-2 and inspect additio.ial C-2 Pksg delective tubes 4S tubes in this S. G. Pestosen action for C-3 C-3 sesult of first w sample N
# Perfosm action for
# C-3 C-3 result of first NM
' sample C-3 IH5Pect all tubes in All other this S. G., plug de- S. G.s are nm>e N/A fi/A k' lective tubes and inspect 2S tubes in C-1 Sonw S. G.s Poefosen action gur each other S. G- N/A f1/A C- 2 but no C-2 result of 5eco'kl acklitional sample Prompt notification S. G. a's to NRC gwauant C-3 to specification Ad.jitional Inspect all tubes in 6.9.1 S. G. is C-3 each S. G. a'Mi Ph'9 delective tubes.
Prompt notification N/A N/A to NilC pussuant to specilication fi.9.1 l
"'"''"'"""'"""'*"">'""*'*""'""*'*8"i'"*"""'""d"*"'"'*""5""*d S - 3n"s "" dosing an enspection h
O sJ Sf
REACTOR COOLANT SYSTEN I
)
3/4.4.6 REACTOR COOLANT SYSTEM LEAXAGE LEAXAGE DETECTION S(STEMS LIMITING CONDITION FOR OPERATION 3.4.6.1 The following Reactor Coolant System leakage detection systems shall be OPERABLE:
- a. The containment atmosphere (gaseous-cr p:rticd ate) radioactivity monitoring system,
- b. The containment;;ac; sump level and flow monitoring system, and
- -:.,, s . ,,, vd ea ~ *" 2 * ' ' .' .' ., , ,
- c. Either the (containment aw+e-cooler condensate f'r rate') or a ccntainment atmosphere Cgas" "s er particulate). radioactivity monitoring system.
APPLICABILITY: MCDES 1, 2, 3 and 4 ACTION: With only two of the above required leakage detection systems OPERABLE, operation may continue for up to 30 days provided grab samoles of the contain-ment atmosphere are obtained and analyzed at least once per 24 hours unen the required gaseous or particulate radioactive monitoring system is inoperacle; othemise, be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the folicwing 30 hours. SURVEILLANCE REOUIREMENTS 4.4.6.1 The leakage detection systems shall be demonstrated OPERABLE by:
- a. Containment atmosphere (gaseous and/or particulate) monitoring i
l system performance of CHANNEL CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST at the frecuencies specified in Table 4.3-3,
- b. Containment ;::'at sump level and flow monitoring system performance of CHANNEL CALIBRATION at least once per 18 months,
- c. (Sym.ify :ppr:;;ricts 3ur,ei;;esice test 34epend49-upom-the-type of
.e aop m m..::r gs* selected.)
(c ,, s,, ,, ,, ,, y se M.,s'<., G,,.a,,w tv sr.d , r.,,, A /i r. / - c . . +, y -
> , A ,., y e rferm,,-n ef c/MM'El CALTFRATT O <*
!aos r em ,n r / S mcnth c . .
O W-STS
~ 3/4 4- NGV 2 1931
/7
O REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION
- 3. 4. 5. 2 Reactor Coolant System leakage shall be limited to:
- a. No PRESSURE BOUNDARY LEAKAGE,
- b. I GPM UNIDENTIFIED LEAKAGE,
- c. 1 GPM total primary-to-secondary leakage through all steam generators 64. i;; Mted ' x tt:...___ .. .-.....,..__.nd (500) gallons per day through any one steam generator.not-hcht:d
- f. e One Ree;ter Coo k67. Cy:t- ,
- d. 10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System, and
- e. M# GPM CONTROLLED LEAKAGE at a Reactor Coolant System pressure of Fl.TS e 20 psig.
J~
- f. I'GPM leakage at a Reactor Coolant System pressure of 2235 : 20 psig O frcm any Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-1.
APPLICABILITY: MODES 1, 2, 3, and 4. ACTION:
- a. With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT STANDBY within 6 hours and in COLD SHUTDOWN within the following 30 hours.
- b. With any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE and leakage from Reactor Coolant System Pressure Isolation Valves, reduce the leakage rate to within limits within 4 hours or be in at least HOT STAN08Y within the next 6 hours and in COLD SHUTDOWN within the following l 30 hours.
- c. With any Reactor Coolant System Pressure Isolation Valve leakage greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours by use of at least two closed manual or deactivated automatic valves, or be in at least HOT STANOBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
l l O W-STS 3/4 4-/f gy, eg;
'~
jy / $
REACTOR COOLANT SYSTEM SURVEILLANCE REOL'IREMENTS 4.4.6.2.1 Reactor Coolant System leakages shall be demonstrated to be within each of the above limits by:
- a. Monitoring the containment atmosphere [ gaseous cr ;;rticukte}-
j radioactivity monitor at least once per 12 hours.
- b. Monitoring the containment ;::'at sump inventory and discharge at least once per 12 hours.
- c. . Measurement of the CONTROLLED LEAXAGE to the reactor coolant pump seals when the Reactor Coolant System pressure is 2235 t 20 psig at least once per 31 days. 4 & th: ::e! a*
- 9 '""a 7"11y c;en. The provisions of Specification 4.0.4 are not applicable for entr/ into MODE 3 or 4
- d. Performance of a Reactor Coolant System water inventory balance at least once per 72 hours.
- e. Monitoring the reactor head flange leakoff system at least once per 24 hours.
4.4.6.2.2 Each Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-1 shall be demonstrated OPERABLE pursuant to Specification 4.0.5, except that in lieu of any leakage testing required by Specification 4.0.5, each valve shall be demonstrated OPERABLE by verifying leakage to be within l its limit:
- a. At least once per 18 months.
- b. Prior to entering MODE 2 whenever the plant has been in COLD SHUTDCWN for 72 hours or more and if leakage testing has not been l
performed in the previous 9 months.
- c. Prior to returning the valve to service following maintenance, repair or replacement work on the valve.
- d. Within 24 hours following valve actuation due to automatic or manual action or flow through the valve.
The provisions of Specification 4.0.4 are not applicable fer entry into MODE 3 or 4. l l l l W-STS 3/4 4-)f, NOV 2 S Ad*fy i l __ _ . _ _ - _ _ - _ _ _ -
TABLE 3.4-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES VALVE NUMBER FUNCTION MC-1562-2.0 NI60 Accumulator Discharge NI71 Accumulator Discharge NI59 Accumulator Discharge LNI70 Accumulator Discharge MC-1562-2.1 1 NIB 2 Accumulator Discharge lNI94 Accumulator Discharge "NI81 Accumulator Discharge 1NI93 Accumulator Discharge
~
MC-1562-3.0 p. iNI159
}NI156 M *- Safety Injection (Hot Leg)
Safety Injection (Hot leg) O }NI128 gr /.2 7 Safety Injection (Hot Leg) INI124 Safety Injection (Hot Leg) b LNI160
- NI157 8I "g SI /3M Safety Injection (Hot Leg) .%
.j Safety Injection (Hot Leg) lNI126 Safety Injection (Hot Leg)
MC-1562-3.1 INI165 Safety Injection / Residual Heat Removal (Cold Leg) h1167 Safety Injection / Residual Heat Removal (Cold Leg) 1/4I169 Safety Injection / Residual Heat Removal (Cold Leg) hNIl71 Safety Injection / Residual Heat Removal (Cold Leg) 1 d.nil nil7675 Safety Injection / Residual Heat Removal (Cold Leg) Safety Injection / Residual Heat Removal (Cold Leg) 2I180 Safety Injection / Residual Heat Removal (Cold Leg) pIl81 Safety Injection / Residual Heat Removal (Cold Leg) MC-1562-4.0 fNI250 Upper Head Injection i
'JNI251 Upper Head Injection NI252 Upper Head Injection 1253 Upper Head Injection NI249 Upper Head Injection INI248 Upper Head Injection MC-1561-1.0
$NDIB*
' Residual Heat Removal INO2A* Residual Heat Removal
" Testing per Section 4.4.7.2.2.d not applicable due to positive indication of valve position in Control Room.
McGUIRE - UNIT 1, 3/4 4-p p h2 f ,g ;y 2 C JUN 1981 l
T. s.
,,.,ew4***
*~
O. ~ emuy$$2%y //d sig ee - vtiVENUMBER v -
; , c ,z e & <J ,
=-
4
- / .
fyey/C WJ' f?Y ~ S a- . I
;I gs 4
O L'
" T I
t
)
3;cy 2 19 S1 ( p/4-M4/ esu.
REACTOR COOLANT SYSTEM 3/4. 4. 7 CHEMISTRY LIMITING CONDITION FOR OPERATION 3.4.7 limits scecified in Table 3 4-2The a Reactor Coolant Syste chemistry sh ll APPLICABILITf: ce maintainec sitnin the At all times. ACTION: MODES 1, 2, 3, and 4: a. State Limit but within its eter TransientWith in excess :f 'ts Steady any one or more :n mimit, within its Steady State Limit witni est:re tra n 22 following 30 hours. STANDBY within nours othece innext 5 nours at:arsmete
'eas: -07to and i
- b. n COLD SHU :CWN wi:nin tre With any one or more chemistry param t Limit, be in at least HOT STANDBY within 6e er in excess of its Transient witnin the following 30 hours.
At All Other Times: hours and in COLD $HUTDCWN With the concentration of eitner chl or in excess of its Transient LimitCoolant System in excess of i less than or equal to 500 psig , reduce the pressur4:er p mssure toata Limit f structural integrity , ifof applicaole, the Reactorand per'orm Coolant an engineering Sevaluation to d Reactor Coolant System remains accept of-limit condition on the . to increasing the pressurizer pressu ystem; determine that the proceeding to MODE 4. acle for continued oceraticn prior re above 500 osig or orior to SURVEILLANCE RECUIREMENTS 4.4.7 the limits by analysis of thosea param tThe Reactor Coolant System c Table 4.4-3. I e ers at the frecuencies specified inbe { determined to b -eSTS O 3/4 4-24 w NOV 2 '937 f
_ma &_ ___u-_Aw .MA .----4*a5-ed i Mm- A d8L*-2--+a43+5Ww Me - 4*ha' -.E+ lea *---4 4EAd h"d4-Wh-- 4su- -.4 A de a-E E amaa.- *- .J em
*#WW ' W *-MH**
- 6 - -.mq y pg & w ,_ymw
!l l y LEA 4-X
/ ,f' j REACTOR COOLANT / Y$T /R URE SO(.ATU#TALV!!S/ t
.NALVEN ER yv yn C TI 7v w
i ! O [, b [
/, -
- , twic vf fup e -
. .J e r_- ! l 1 O i i : i i t
~
O p/4g. PSTS Ngy 3 19S1 p
'y-u-e-----r-e---en-w+ w m t wm - gw y -=ywww mi- m -ggg - w% m Twgww- ww ww__ _ mee c eemves *w wwwu a mwe -m* WN-e--**-e'*-i--eee--w -r+ --
REACTOR COOLANT SYSTEM l 3/4.4.7 CHEMISTRY l l LIMITING CONDITION FOR OPERATION 3.4.7 The Reactor Coolant System chemistry shall be maintained within the . limits specified in Table 3.4-2. APPLICABILITY: At all times. , ACTION: MODES 1, 2, 3, and 4: ,
- a. With any one or more chemistry carameter in excess of its Steady State Limit but within its Transient Limit, restore tne parameter to within its Steady State Limit within 24 hours or be in at least HOT STANOBY within the next 6 hours and in COLD SHUTCGhN wi:nin :ne following 30 hours.
- b. With any one or more chemistry parameter in excess of its Transient Limit, be in at least HOT STANDBY within 6 hours and in COLD SHUTOCWN within the following 30 hours.
At All Other Times: : With the concentration of either chloride or fluoride in the Reactor Coolant System in excess of its Steady State Limit for more than 24 hours or in excess of its Transient Limit, reduce the pressurizer pressure to less than or equal to 500 psig, if acplicable, and perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity of the Reactor Coolant System; determine that the Reactor Coolant System remains acceptable for continued oceration prior to increasing the pressurizer pressure above 500 psig or prior to proceeding to MODE 4. SURVEILLANCE RECUIREMENTS 4.4.7 The Reactor Coolant System chemistry shall be determined to be within the limits by analysis of those parameters at the frequencies specified in Table 4.4-3. 2 NOV 0 i31 W-STS
' 3/4 4-24 '
.g 2f 9
O TABLE 3.4-2 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS STEADY STATE TRANSIENT PARAMETER LIMIT LIMIT DISSOLVED OXYGEN
- 1 0.10 ppm i 1.00 ppm CHLORIDE 1 0.15 ppm 5 1.50 ppm FLUORIDE $ 0.15 ppm i 1.50 ppm l
1 O
" Limit not applicaole with T,yg less than or equal to 250*F.
t O PSTS 3/4 4-5 ., s NCV 0 1981 A3
,,m., , . , , _ - , . - _ ,m_. ., -
1 i 1 iABLE 4.4-3 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS SURVEILLANCE REQUIREMENTS SAMPLE AND PARAMETER ANALYSIS FREOUENCY DISSOLVED OXYGEN
- At least once per 72 hours CHLORIDE At least once per 72 hours FLUORIDE At least once per 72 hours
^Not requitec w1:n T less than or equal to 250*F O
avg I 3/4 4-JE r;3y 3
'f-STS p .2 g 1931
O REACTOR COOLANT SYSTEM 3/4.4.8 SPECIFIC ACTIVITY , LIMITING CONDITION FOR OPERATION 3.4.8 The specific activity of the primary coolant shall be limited to: l a. Less than or eoual to 1.0 microcurie # and #pergramDOSEEQUIVALENTI-131,
- b. Less than or equal to 100/E microcuries per gram.
APPLICABILITY: MODES 1, 2, 3, 4, and 5. ACTION: MODES 1, 2 and 3*:
- a. k"th the specific activity of the primary coolant greater than 1.0 microcurie per gram DOSE EQUIVALENT I-131 but within the allowable limit (below and to the left of the line) shown on Figure 3.4-1, operation may continue for up to 48 hours provided that the cumula-O tive operating time under these circumstances does not exceed 800 hours in any consecutive 12-month period. With the total cumulative operating time at a primary coolant specific activity greater than 1.0 microcurie per gram 00SE EQUIVALENT I-131 exceeding 500 hours in any consecutive 6-month period, prepare and suomit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days indicating the number of hours above this limit. The provisions of Specification 3.0.4 are not applicable.
- b. With the specific activity of the primary coolant greater than 1.0 microcurie per gram DOSE EQUIVALENT I-131 for more than 48 hours j during one continuous time interval or exceeding the limit line shown i on Figure 3.4-1, be in at least HOT STANDBY with T avg less than 500*F
! within 6 hours. . ..
- c. With the specific activity of the primary coolant greater than 100/E microcuries per gram, be in at least HOT STANOBY with T**9 less than 500*F within 6 hours.
- Witn T,yg greater r equal to 500 *F.
O PSTS . 3/4 4-X g - tav nat
-W---
REACTOR COOLANT SYSTEM ACTION: (Continuec} MODES 1, 2, 3, 4, and 5:
- a. With the specific activity of the primary coolant greater than 1.0 microcurie per gram DOSE EQUIVALENT I-131 or greater than IC0/E microcuries per gram, perform the sampling and analysis requirements of item 4a of Table 4.4-4 until the specific activity of the primary coalant is restored to within its limits. A REPORTA8LE OCCURRENCE shall be prepared and submitted to the Commission pursuant to Specifi-cstion 6.9.1. This report shall contain the results of the specific activity analyses together with the following information:
- 1. Reactor power history starting 48 hours prior to the first sample in which the limit was exceeded,
- 2. Fuel burnup by core region,
- 3. Clean-up flow history starting 48 hours prior to the first sample in whicn tne limit was exceeded,
- 4. History of de gassing operations, if any, starting 48 hours prior to the first sample in which the limit was exceeded, and
- 5. The time duration when the specific activity of the primary coolant exceeded 1.0 microcurie per gram 00SE EQUIVALENT I-131.
l l SURVEILLANCE REOUIREMENTS { j 4.4.8 The specific activity of the primary coolant shall be cetermined to be I within the limits by performance of the sampling and analysis program of Table 4.4-4. l l l O W-STS 3/4 4-JE g M2 W
O O O TABLE 4.4-4
'T PRIMARY C00LANI SPECIFIC ACTIVITY SAMPLE
- AND ARAMIFPRERAM l
SAMPLE AND ANALYSIS MODES IN WillCil SAMPLE TYPE OF MEASUREMENT FREQUENCY AND ANALYSIS REQUIRED AND ANALYSIS
, 1. Gross Activity Determination At least once per 72 hours 1, 2, 3, 4 1 per 14 days I
- 2. Isotopic Analysis for DOSE EQUIVA-LENT I-131 Concentration
- 3. Radiochemical for E Determination 1 per 6 months
- 1 Isotopic Analysis for Iodine a) Once per 4 hours, 1,2,3,4,S 4.
Including I-131, I-133, and I-135 whenever the specific activity exceeds 1.0 w pCl/ gram DOSE
) EQUIVALENT I-131 or 100 6 pCi/ gram, and b) One sample between 2 1,2,3
( and 6 hours following a IllERMAL POWER change o. exceeding 15 percent of the RATED lilERMAL POWiR within a 1-hour ' period.
#U ntil the specific activity of the primary coolant system is restored within its limits.
- Sample to be taken after a minimum of 2 EFPD and 20 days of POWER OPERATION have elapsed since reactor was last subcritical for 48 hours or longer.
5 to k
~
)
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,,,, 1 ,. . . . .. . i,,, , , i i i i . . . . .
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, . . g . . . . . .. , .. ..ii i... .. ,
. T. , , . . . . .i ,. . . i. ,e e . .
l
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, . . , . . i s' . .. . , , . .' . i . . '. .' i . .' '.
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i
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. . . . . .s, , , , . , ,
, UNACCEPTABLE - * ' '
. . . . . . Ai ., i 6 i i . i 4 , , ., . . , ,,x ,* i , , ,,e OPERATION llll c . , . . . . .. .x ...i . . . . . . . . , , ....
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. . . . . . , . ... , , i i ,1 , 6 . ,, .... , , , ,
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m . . . , . . . . . ,. , , . , . si . . .. i.., . 4 , ,
. . . . ., i . , ,, , it 6 , e5 , e f . i+t i . . . .
. . . . . , , . 6 . , , . , 6 i , .\ . . . 6 . . : i 6 . . i g- 100: . . , . , , , . ... ... . . ... (. . , . . . . . , , ,
s . . . . . . i 6 , 6 . ... t . .. , x... i . . , , . .
. . . i . . . , i i . . . , , . . ii a, . , . . i . . . . ,
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ACCEPTABLE i++ i + * ' a - 2,u , , ,,. i . , , .' i . , , . . . . . .
.a g . . OPERATION . . . . . ., ,.,. . . . , , ,
< , , , , . . . . . . , , . . . . . 4 . , . . . . . ,
> . . . . . . . , . . . . i i. , . . . , , , , ; . . , , ,
3 g
, , 6 ,
.,. i i
i , . .
. . , , . . . . . . i .. .
i , . i . , .,,,
...A, i . . . . i , , ,
,, , , , . . . . . . . , ... . . 4 . . . . . .... ....
4 . . . , , , i i,, ,, , , , , , , , , , , , , , , , 8 , . . .
, . , i e , ,
20 30 40 50 80 70 80 90 100 PERCENT OF RATED THERMAL POWER FIGURE 3.41 DOSE EQUIVALENT l-131 Primary Coolant Specific Activity Limit Versus ! Percent of RATED THERMAL POWER with the Primary Coolant Specific 9l l Activity >1.0gCi/ gram Dose Equivalent 1-131
'-STS f 3/4 4-3<r N0'l 2 1981 X> -
REACTOR COOLANT SYSTEM 3/4.4.9 PRESSURE / TEMPERATURE LIMITS REACTOR COOLANT SYSTEM l LIMITING CONDITION FOR OPERATION 3.4.9.1 The Reactor Coolant System (except the pressurizer) temperature and pressure shall be-limited in accordance with the limit lines shown on Figures 3.4-2 and 3.4-3 during heatup, cooldown, criticality, and inservice leak and hydrostatic testing with:
- a. A maximum heatup of (100)*F in any 1-hour period.
- b. A maximum cooldown of (100)*F in any 1-hour period.
- c. A maximum temperature change of less than or equal to (10)*F in any 1-hour period during inservice hydrostatic and leak testing operations above the heatup and cooldown limit curves.
APPLICABILITY: At all times. ACTION: With any of the above limits exceeded, restore the temperature and/or pressure to within the limit within 30 minutes; perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity of the Reactor Coolant System; determine that the Reactor Coolant System remains acceptable for continued operation or be in at least HOT STANDBY within the next 6 hours and reduce the RCS T and pressure to less than 200*F and 500 psig, respectively, within th8V9o11owing 30 hours. SURVEILLANCE REQUIREMENTS 4'.4.9.1.1 The Reactor Coolant System temperature and pressure shall be determined to be within the limits at least once per 30 minutes during system heatup, cooldown, and inservice leak and hydrostatic testing operations. 4.4.9.1.2 The reactor vessel material irradiation surveillance specimens shall be removed and examined, to determine changes in material properties, as required by 10 CFR 50, Appendix H in accordance with the schedule in < Table 4.4-5. The results of these examinations shall be used to update Figures 3.4-2 and 3.4-3. O PSTS . 3/4 4-X yy NOV 2 1981 l l . . - . .
. _ . _ . . _ - . _ . . . - - - , _ _ . . . - - - , . - - - . . , . =. ,- - - -
TABLE 4.4-5 ; 39 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM - WITHDRAWAL SCHEDULE 3 CAPSULE VESSEL LEAD NUMBER LOCATION FACTOR Willi 0RAWAL TlHE (EFPY) ll sc 3.6 y ss'. s ' 3. 0 W in
' 36 '
"f
'd i
X y a 38. S
- 3. o ,
z n s. c e. A w 4) ff, // a s;, . s- j'r N r /'* ** "' Y li no a .,- 5/ai// }.. 7, . s Ja/r./ /; l9 o'/bbau1:l f fe// sun'ay +4 c. fin f- re foe Isiy
' eu A/y ct .
s S
-[A O '
O O
l
- D # .
f 3 2600 " TmTiin u inini u n iin u n u u n ni n in in u u u n u n iu u n in u I g CullVE APPLICABLE FOliilEATUP HATES l o UP TO 1GO F/lut FOft Tile SEHVICE PEttlOD ( E UP 1010 EFPY, AND CONTAINS MAllGINS MINIMUM INSEltVICE , i l l [ $ OF 10" F AND 60 PSIG FOtt POSSIBLE LE AK TEST l(f I I l l
. 5 2200 INSTituMENT EI4 Holts IEWEHATUHE
; g l E lilllllillilillilillllllllll!!!!lllllllllililllllilllillllillllilllll l -l E !b MAT Elll AL S B ASIS l l l
l l
',y g 2000 CON TitOL LING MATElll AL - WE LD METAL I g' f p'
n PitOSPitollus CONTEta T - 0 013 Wi% l l COPPEll CONTENT 0.30 WT% ' i 1800 IITNor oftlGINAL,0*F i p a- UNACCEPTABLE i itTupy AFTEH 10 EFPY 1/4T,124*F OPERAllON ' h 1600 3/4T, 85* F
/
l 1 D / i ACCEPTABLE b 1400 ' ' p l h l j PRESSUftE IEMPEllATullt. , o 1200 i { LIMIT Folt itEATUP It ATES v , O UP TO 100* F/lill X / i i 1000 , J , f A u .' b 800 ' '
- CHITICALITY j
[ ,
; LIMIT us W Q 600
,e l
S $ 2 400 200 0 l 0 50 100 lbo 200 250 300 350 400 INDICAlED AVEllAGE HEACTOll COOLANT SYSTEM TEMPEll ATUHE (*F) FIGullE 3.4 2 ItE ACTOlt COOLAN T SYSTEM PHESSUHE - T EMPEHATullE LIMITS FOll llEATUP ltATES UP 10 100 0F/110011 CHITICALITY LIMIT AND llYDilOSTATIC IEST LIMIT '
k 2m m j;gggglJ;igj;g[j g jg;;;gggjjj;;gj g;g ggg gg g gi;;gg j gigigg g gg g g gig;;j . i CUHVE APPLICADLE Foil Tile SERVICE! m PEfilOD UP 1010 LFPY AND CONT Alf45 l 2400
, MAllGINS OF 10*F AND 60 PSIG IOil l qc POSSlut E INSillHMENT LilllOllS l l
dE 22m :lllllllllllltlllllllllllllllllljllllljlllljllllllllllljlljjllljl j , c MAT Eft l At S B ASIS ll ).l --# g g g CONTHOLLING MATERIAL -WELD METAL - I 20M ' l
] PilOSPilOHUS CONTENT - 0.013 WT% l m COPPE H CONTENT - 0.30 WT%
9 l I 3 1800 HTuoy Of tlGIN AL. 0*F l l U HTuoy AFTEH 10 EFPY 1/4T.124*F ll [ 1600 3/4 T. 8b* F 1
/ a 3 UNACCEPTABLE '1 h
f OPEHATION I p ACCEPTABLE g 1400 / OPEll ATION j' l pl l u , ,, c., j 1200 f ,i
} O
,r Q 1000 pg' ESS'UHE - TEMPERATuflE, '
s i g
', 0 h o LIMITS 1 N li, lii i
l
< 800 g j 4 \
un ;j,jql;ijjl!ll o COOLDOWN g 6" HAveff/iiH , ., p:f, Jh,c ; i g 3 0 Ilo - C '--t:F ' '. . 400 25 50 y o" , ,c l 1
-2 j'g " F'4.c 18 l l l
2m j l lf ll! l l, ; ,1 l] l jj O
! ! lh!i!n !, L L llll, , l !!h 4 i F :l !L . , !
ji
, 1 i i 0 60 100 150 200 250 300 360 400 INDICA 1ED AVER AGE ilE ACTOlt COOL ANT SYSTEM TEMPEllATullE (*F)
FIGullE 3 4 3 HE ACToll COOLANT SYSTEM PRESstlHE - TEMPEllATullE LIMITS VEllSils COOLDOWN llATES
,- m ,- ~
J J
O O O s
'Y
ui 2am ,i in g, ;;; ;;;; ;n, ]; hl"!. h
!i;,i !! Pi1 ESSURE - TEMPERAIUllE ij [I l l l l "li! "lb!i
'h 7?
it! I!!! i;i'i iii!
'l
.i; d=,i 9 iUi !!! 9 i *! ?!' i 5 l i 'llI 26m "
~
N Y
- N N'?
= =
);,
ae u
% .1 ::Js a
;i.
=
I bI. LIMIT DUlllNG es TIONS llYDilOSTATIC: .-[ Y Y g, s:- +
~
N.... J .1
- .a.
23 .T "ESTING OPEllA.g.aJ.
- ~-
, .2. _. _
;.c . . . # :.14 ,
k 2400 CURVES'AbLICkBLE FOR SElldiCh '
' i '"
_ PERIODS UP TO (15) EFPY (AND CONTAIN -
++ + ..
9 -i? b ifl [f {j hhk ; eij ill; ih f:! E i 9 2200 MARGINS OF 10* F AND 60 PSIG FOlt w H l'j I 'il f.:lj
=!
ACOPbd' ! ' i E ' g ] llj'Ih' POSSillLE INSTRUMENT ERRORS) _ .; . 8
- c 1. ib '! ,3 di ! , h 1
' .: REGION FOR rn g j j g'
- 8
.g:i.g: += i;-i"
.> .:I' lc~ p i su 2000 ".I;
=
"IlYDROSTATIC l l
j g ! fik -4 IN A IONS b. h. MATERIAL kIS. l h l l .1 .h [ l f 1800 CONTROLLING MATERIAL-(RV LOWER SilELL) *4 ih 9 + COPPER CONTENT: (0.16%) '- d i : M l,
, l l
,I h l}h!ill fll. '
j' [ .;i UNAC'CE'PTAtiLE I i i $i il'! IIIf iifi 0
"!i k h l
g 1600 PilOSPilORUS CONTENT: (0.08%) b 77 OPE R ATION h l 's
;i " "' E fIi b' su l
RT NDT ORIGINAL: (10* F) iii 5 l;I. m: iiii @ !pi Yy .
.]j l l l f !
1400 RT NDTAFTER (15) EFPY @ 1/4T = (109* F)lieh 1.' h hi!il ;i p$i l [)d " ; g "g g y RT g AFTER (15) EFPY @ 3/4T = (77* F) - j]j :,y} .f-j : 3l l l j 3 [p[ h 1200 T "5 lEi@ llU ; "'. y44 h I !
'l e, ,
Isl 1
'j{ f,[ H }i P' F 3 :.i:
@N
'i I 'Uj [EI g' 2}; } f h"L' !}ii .ii.' :s li!jij Fy [
CRITICALITY LIMIT j! q
..! Iili ifil 2:- i U !yl i.fi !!H f2 .' stLp ; .
s g Imo i l t.a iii !!!!
- .. ;:j
! PRESSURE - TEMPERATURE B
. S w i o!! Iiii
{[j ;g- {jjj1;ji
, : il !
g : 1 j,' l i r i ji' ij,: {'} ijjiSb3k k i LIMIT FOR llEATUP flATES' y' 1 ; ;;
$ @"'S 'N UP TO (60*
i g j ! o 800 ;35[, ;N I ' ill .i : ' N,j .' ]: F"h, 1 , 1J i-F/HR)gw]g/ b
;;i !He "
t l ! TF ..
' ty m l .
g
,, h. ' lju i Ij k "" J jl ACCEPTABLE I
it I y h ~ll j h, d ) h, l.[ OPERATION
,f 400 g -
p n , Tills FIGURE FOft ILLUSTRATlON ONLY s x j ij :,.; i
.g l
i' DO NOT USE FOR OPEllATION 2m g j ;i gg j ;g j g t)j jjg g j
)
a lin lii!h !N; D. l '
!l l I l 'ii! l i iLi ! -,
i h;l !!, I i , I j, 7 0 50 100 150 200 250 300 350 400 N 4 AVERAGE REACTOR COOLANT SYSTEM 1 EMPERATURE (* F)
" Figure 3.4-2 Reactor Coolant System Pressure - Temperature Limits Venus 60* F/Ilour S lleatup Rete - Criticality Limit and ifydrostatic Test Limit in
\
b
i 1 s ! N 3000 5 CURVE APPLICABLE FOR THE SERVICE _ . . _ _ _ M E=l PERIOD'UP TO (12) EFPY (AND CONTAINS m._._. ..._.__ _ ___ ._.__- -. - _ _ ' . . . _ . c MARGINS'OF 10* F AND 60 PSIG FOR --"r==:===-= v'POS --'~I I TE i- U 2.5 F =,_3:'.:.
":F' 2600 .:.u.e. ..=;;=.-- SIBLE ERRORS) .
__ . - - - . ......:._ _+--
,:: 2.: = *:**:--* . . _ . . _..:
-....-...:-'*.:~*-*-*V---.+-
; ., , ., 3-.. .._ .- -.. -- - ----+.---
I. ..2=_:--_.a--.-
, 2400 THIS FIGURE FOR ILLUSTRATION ONLY
. j. . 2. .: . . . _. . .t.n...c
.. . . : ==: _. _
t C l DO NOT USE FOR OPERATION E-i m 1. _:f._ p"nO .. .:..: u. _=. " J=. . 4: 't 43f:ii :% . ._._ __..._._ :--G :Ei:2:-- -6 ??:~ : ~ f "*""-d T ~ :- i e ..i;.: : 2.L=ii 3-'- ~ ~ 7: 1 "Ei!-
- 3 2000 !: -. - -- --- . ;=.=-!; - .=' "__ F ::252.:i. :-" in.;5=i .fiiii .J 2: . !.. , :..
.. .:. f.
g
- 4.-=:. a:33 _
"a. a : . a 4 f:- .:-
g 1800
!. :'i ~ I:~ai: d .iSE UNACCEPTABLE F : i- '/ L l
~"
!- r - ' F'"it:E =- OPERATION .i f: ! i i 3 i i :4: l - #.1_ -.J._. .,. . L i - l- t / -
$ -:1- :1.ul-i :21 is.+i =i.iztT-" ~;"_Cu 4:i =-h .= 42:+:..v ./ : -" '"
$ 1* r::iu :::=:-r- _-~__ ____._. ====f ' ui'i u?-E : i.~5L 2 fh 4_ ." ; I ~ il E 1400 - -.. -..-
$ ' 1:? "+"9d PRESSURE - TEMPERATURE L'ii-f..- . ACCEPTABLE .:
< t < 2,.':: : -
~
LIMITS s ; ff - OPERATION - Y) I2" -
- j. q.g :tii eif uij:pis.::q i,: 2:_N .g.:i,;:. n. l . .- : =;- -
( 0 1000 t
' 4: --4--
' ,.i- :iE:!::,ii -
' ~ ~ -
-! --: M -t i ;. . " n
~~
g ! !:. ;t.'r. i ;;}t." 3L . - "1 . g ;[= 4 ; .i . i. ' ; . - _. l g
-e -,
0 COOLCOWN RATE I. " .:ui I. == -
= 4- 1 3 TL, :
< 800 -==..--'..-. ".- w" E-_- -w~ _. -_.- -. -." . " .
~ 4 . .. .'_. - . . . -
g.F HR) w -- - w"A TE R tA t s Asis. ' ~ "' ~ ' - " ""'" ' a g .
. 1..::. _
* : .. . _ . . . . . . ...;..g... -- - __ j p "_ .a.r ..: CONTROLUNG MATERIAL- =
- 4 0 ;; . - - _-- - ..
P
. ... _ .. .. :--i=:i iRuAcTon vessel INTERMEDIATE SHELW }
.:j #3:: :idi.J.i." i COPPER: (0.15%), PHOSPHORUS: (0.08%)
400 _ RTNOTORIGINAL: (46*FI
- -,- . 40 ((f. --._::~____----__ - :.::..- .: .
200 1.100
%r < - . -. . *:.,; _=_ .
, , _ , 7. -
- . "--" 2.~ ' _ _;. " ; RTNOTA
_7:7 ny,,r ,7:n A 02) WW4 Tams % a neig,,y,3/4T-ris*P) g i
- Ei: f _ Ji:-!!.=iEM==-t=.
/ O
. :. .i: fin -isin!I
~ - ~ -
nii;_E-L=:r3--'.".~ "- -r
-~
~-
._- O:Efi H;in-
.!!. --. . Ki' : ~
'l
!- ~ ' -
F-
....j I : ' -i : '-
20 100 200 100 i l AVERAGE REACTOR COOLANT SYSTEM TEMPERATURE (* F) .
'N N Figsre 3.4-3 Reactor Coolant System Pressure - Teraperature Limits Versus Cooldown Rates l 9 pc (C !' '
i O W-STS
- M/4 -4'-34' ,
,10V 2 1987
l l REACTOR COOLANT SYSTEM PRESSURIZER LIMITING CONDITION FOR OPERATION 3.4.9.2 The pressurizer temperature shall be limited to:
- a. A maximum heatup of (100)*F in any 1-hour period,
- b. A maximum cooldown of (200)*F in any 1-hour period, and
- c. A maximum spray water temperature differential of (320)*F.
APPLICABILITY: At all times. ACTION: With tne pressuri:er temoerature limits in excess of any of tne above limits, restere the temperature to within the limits within 30 minutes; perform an , engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity of the pressurizer; determine that the pressurizer remains acceptable for continued operation or be in at least HOT STAND 8Y within the next 6 hours and reduce the pressurizer pressure to less than 500 psig (( within the following 30 hours. SURVEILLANCE REOUIREMENTS 4.4.9.2 The pressurizer temperatures shall be determined to be within the limits at least once per 30 minutes during system heatup or cooldown. The spray water temperature differential shall be determined to be within the limit at least once per 12 hours during auxiliary spray operation. l l lO W-STS 3/4 4-)B' 52- NOV 0 lo81
~
drT
, . - - . _ ,- r- - . - -
-- .. . . - - - . . . . . . 1 l
REACTOR COOLANT SYSTEM l OVERPRESSURE PROTECTION SYSTEMS ! LIMITING CONDITICN FOR OPERATION 3.4.9.3 At least one of the following overpressure protection systems shall I be OPERABLE: 1 l
- a. Two power operated relief valves (PORVs) with a lift setting of less than or equal to g ) psig, or
- b. The Reactor Coolant System (RCS) depressurized with an RCS vent of greater than or equal to (-t square inches.
APPLICABILITY: MODE 4 when the temperature of any RCS cold leg is less than or equal to (MT)*F, MODE 5 and MODE 6 with the reactor vessel head on. geo ACTION:
- a. With one PORV inoperable, restore the inoperable PORV to OPERABLE status within 7 days or depressurize and vent the RCS through a square inch vent (s) within the next 8 hours.
- b. With both PORVs inoperable, depressurize and vent the RCS tnrough a
% I N square inch vent (s) within 8 hours.
- c. In the event either the PORVs or the RCS vent (s) are used to mitigate an RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the PORVs or vent (s) on the transient, and any corrective action necessary to prevent recurrence.
- d. The provisions of Specification 3.0.4 are not applicable.
l l 9 l W-STS 3/4 4-)( 3_5 NOV 2 1981 l M l
O U REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS 4.4.9.3.1 Each PORV shall be demonstrated OPERABLE by:
- a. Perfornunce of a ANALOG CHANNEL OPERATIONAL TEST on the PORV actuation enannel, but excluding valve operation, within 31 days prior to entering a conaition in wnich the PORV is requirec OPERABLE and at least once per 31 days thereafter when tne PORV is required OPERABLE.
- b. Performance of a CHANNEL CALIERATION on the PORV actuation thannel at least once per 18 months.
- c. Verifying tne PORV isolation valve is open at least once oer 72 hours wnen the PORV is being used for overoressure crotection.
- d. Testing pursuant to Specification 4.0.5.
4.4.9.3.2 The RCS vent (s) shall be verified to be open at least once per 12 hours
- when the vent (s) is being used for overpressure protection.
O "Except wnen tne vent pathway is provided with a valve which is locked, sealed, or othemise secured in the open position, then verify these valves open at least once per 31 days. O W-STS 3/44-p7 t '/ N0Y 2 1981
~
x l
REACTOR COOLANT SYSTEM 3/4.4.10 STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION f 3.4.10 The structural integrity of ASME Code Class 1, 2 and 3 ccmponents j shall be maintained in accordance with Specification 4.4.10. j APPLICABILITY: All MODES. ACTION:
- a. With the structural integrity of any ASME Code Class 1 component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature more than 50*F above the minimum temperature required by NOT considerations.
- b. With the structural integrity of any ASME Code Class 2 cc=ponent(s) not conforming to the above requirements, restore the structural integrity of the affected ccmponent(s) to within its limit or isolate the affected ccaponent(s) prior to increasing the Reactor Coolant System temperature above 200*F.
- c. With the structural integrity of any ASME Code Class 3 component (s) not conforming to the above requirements, restore the structural
' integrity of the affected component (s) to within its limit or isolate the affected component (s) from service.
- d. The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.4.10 In addition to the requirements of Specification 4.0.5, each reactor coolant pump flywheel shall be inspected per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975. I O l l W-STS 3/4 4- g g5- , p- NOV 2 lost ;
I O 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS LIMITING CONDITION FOR OPERATION c:li lui wee...._
- 3. 5.1,/ Each rx;b.
/ jecb'rn , .._-accumulator shall be OPERA 8LE with:
- a. The isolation valve open,
- b. A contained borated water volumn of between M424 / and F'"- gallons,
- c. A boron concentration of between (1900) and (2100) ppm, and
! d. A nitrogen cover pressure of between W 4 and M ' psig. APPLICABILITY: MODES 1, 2, and 3*. ACTION: c.f./ /4 . a >; ' c T' ' ' ,
- a. With onefaccumulator inoperable, except as a result of a closed isolation valve, restore the inoperable accumulator to OPERABLE status within 1-hour or be in at least HOT STANDBY within the next 6 hours and in HOT SHUTDOWN within the following 6 hours,
- e. u '. . ;,i:a h n
- b. With one{ accumulator inoperable due to the isolation valve being j
closed, either immediately open the isolation valve or be in at least HOT STANDBY within 1-hour and in HOT SHUTDOWN within the following 12 hours. l l SURVEILLANCE REQUIREMENTS ut./ /cy ;.da tN!' 4.5.1.1 EacMaccumulatorshallbedemonstratedOPERABLE:
- a. At least once per 12 hours by:
- 1. Verifying, by the absence of alarms, the contained borated water volume and nitrogen cover pressure in the tanks, and cets /q lnje.c.h'in
- 2. Verifyingthateach,jaccumulatorisolationvalveisopen.
" Pressurizer pressure above 1000 psig.
O W-STS 3/4 5-1 NOV 2 01550
EMERGENCY CORE CCOLING SYSTEMS SURVEILLANCE REOUIREMENTS (Continued)
- b. At least once per 31 days and within 6 hours after each solution volume increase of greater than or equal to (1*.' of tank volume) by verifying the boron concentration of the accumulator solution.
- c. At least once per 31 days when the RCS pressure is above 2000 psig by verifying that power co the isolation valve operator is disconnected by removal of the breaker from the circuit.
- d. At least once per 18 months by verifying that each accumulator isolation valve opens automatically under eacn of the following conditions:
- 1. When an actual or a simulated RCS pressure signal exceeds the P-11 (Pressurizer Pressure Block of Safety Infection) setpoint,
- 2. Upon receipt of a safety injection test signal.
uu ky lajern 4.5.1.2 -GaehAaccumulator water level :nd pressure channel shall be cemonstrated OPERABLE: l l
- a. At least once per 31 days by the performance of a ANALOG CHANNEL OPERATIONAL TEST. I
- b. At least once per 18 months by the performance of a CHANNEL CAL 2BRATION.
l O SEP 15181 W-STS 3/4 5-2
r V EMERGENCY CORE COOLING SYSTEMS UPPER HEAD INJECTION ACCUMULATORS LIMITING CONDITION FOR OPERATION
- 3. 5.1. 2 Each upper head injection accumulator system shall be OPERABLE with:
l a. The isolation valves open,
- b. The water-filled accumulator containing a minimum of 1850 cubic feet of boratad water having a concentration of between 1900 and 2100 ppm of coron, and
- c. The nitrogen bearing accumulator pressurized to between 1206 anc 125a ::sig.
APPLICABILITY: MCOES 1, 2 and 3.* ACTION:
- a. With the upper head injection accumulator system incoerable, except i
as a result of a closed isolation valve (s), restore the upper head I - injection accumulator system to OPERABLE status witnin one hcur or d be in at least HOT STANOBY within the next 6 hours and in HOT SnUTDOWN witnin the following 6 nours.
- b. With the upper head injection accumulator system inoperable ::ce to the isolation valve (s) being closed, either immeciately cpen the isolation valve (s) or be in HOT STAN08Y witnin one hour and be in HOT SHUTDOWN within the next 12 nours.
SURVEILLANCE REGUIREMENTS
- 4. 5.1. 2 Each upper head injection accumulator system shall be cemonstrated OPERABLE:
l l a. At least once per 12 hours by: l 1. Verifying the contained borated water volume and nitrogen pressure in the accumulators, and
- 2. Verifying that each accumulator isolation valve is open.
"Pressurl:er Pressure above 1900 psig.
V McGUIRE - UNIT 1 3/4 5-# :Z a OAT 7' 2-
l n
%l EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- b. At least once per 31 days and within 6 hours after each solution l
volume increase of greater than or equal to 1% of tank volume by l verifying the boron concentration of the solution in the water-filled accumulator. 1
- c. At least once per 18 months by:
- 1. Verifying that each accumulator isolation, valve closes autcma-
'~ . ,5 tically when the water level in the 'r Sid.E caObrh'- r.:
s y (,I * -is 73. : 7:r I M inches above the bottom inside edge of the sater-fit 1eogccumulatcr.
- - e,
- 2. Verifying that the total dissolvec nitrogen and air in the water-filled accumulator is less thge 80 SCF per 1800 cuoic feet of water (eouivalent to 5 x 10 ' pounds nitrogen per
;ounds water).
t > s'sc /r . d.' At least once cer 5 years by 8--"'-( tne membrane installed between the watar-fillec and nitrogen cearing accumulators. arm m .f iag. [x]s -that the emovec--me= crane-bursts at-a-dM*erefw+a l prc::ur -ah . t as'. - i N _: 7 ,. , , c t-
** - = _ . _ ,
C.'"*'~',/,' 49,
- ys' Y
. ,,,,./,, ,
- j,, c &ie / r t -
I (., -
,. ,: . . < o? ? S ' ' " ' ~' ^~"
/ .; o 4 -.
s o a e 1 l l . McGUIRE - UNIT 1 3/' '-/ 2 4 ukrr 2-t - _ - - u -
EMERGENCY CORE COOLING SYSTEMS 3/4.5.2 ECCS SUBSYSTEMS - T,yg > 350*F LIMITING CONDITION FOR OPERATIOif 3.5.2 Two independent Emergency Core Cooling System (ECCS) suosystems shall be OPERABLE witn er.ch subsystem comprised of:
- a. One OPERABLE centrifugal charging pumo,
- b. One OPERABLE safety injection pumo (f)4614oo. plan'tfodly), ,
- c. One OPERABLE residual heat removal heat exchanger,
- d. One OPERABLE resicual heat removal pumo, and
- e. An OPERABLE flow path capable of taking suction from the refueling water storage tank on a safety injection signal and automatically transferring suction to the containment sump during the recirculation phase of operation.
APPLICABILITY: MODES 1, 2, and 3. ACTION: i ! a. With one ECCS subsystem inoperable, restore the inoperaole subsystem l to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours and in HOT SHUTDOWN within the following 6 hours,
- b. In the event the ECCS is actuated and injects water into the Reactor l Coolant System, a Special Report shall be prepared and submitted to l the Commission pursuant to Specification 6.9.2 within 90 days describ-l ing the circumstances of the actuation and the total accumulated l actuation cycles to date. The current value of the usage factor for each affected safety injection no::le shall be provided in this Special Report whenever its value exceeds 0.70.
O W-STS 3/4 5 NOV 2 01980
EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:
- a. At least once per 12 hours by verifying that the following valves are in the indicated positions witn power to the valve operators
. removed:
M mserf m Me d ,7w , Valve Number Valve Function Valve Position ]
- a. a. a.
b.
- b. b.
l c. c. c. t _. , b. At least once per 31 days by:
- 1. Verifying that the ECCS piping is full of water by venting the ECCS pump casings and accessible discharge piping high points, and
- 2. Verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or othersise secured in position, is in its correct position.
- c. By a visual inspection which verifies that no loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions. This visual inspection shall be performed:
- 1. For all accessible areas of the containment prior to establish-
! ing CONTAINMENT INTEGRITY, and l
- 2. Of the areas affected within containment at the ecmpletion of each containment entry when CONTAINMENT INTEGRITY is established.
- d. At least once per 18 months by:
- 1. Verifying automatic isolation and interlock action of the RHR.
system from the Reactor Coolant System by ensuring that: a) with a simulated or actual Reactor Coolant System pressure signal gr:: ster than or equal to 425 psig the interlocks prevent the valves from being opened, and b) with a simulated or actual Reactor Coolant System pressure 9,.A, ~ signalQthan or equal toc 680lpsig the interlocks will cause the valves to automatically close A _f /c
- 2. A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by decris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or abnormal corrosion.
O W-STS 3/4 5-4
'NOV 2 togt
i
. l 1
i k EMERGENCYCONh M MS -
/ f , k lTS SURVEILLANCE RE # REMEN
/ - -s
/ / - ,,
,,e ./ /
! f
, 4. 5. 2 Each ECCS su/
/) <
' ,8 '
, .,/ ::s/y-rem/ shall be d.emonstrateMPERA, ,- PEE:
,- ,/. ..
s.Qt JIast once per 12 hours by verifying tb5t tced'ollowik 'Tes are iy the indicated posii g with powe W lfne valve jpepators respved: W g,,j ' Valve Num.ber Valve Function Val 7e N y
,f a. N!162A a. Cold Leg Recirc. a. Ccen y , , 3 .'. - ' b. g NI121A b. Hot Leg Recirc. c. Closed
/ m c. NI1528 c. Hot Leg Recirc. c. Closed i s ' 7 "~ " d. NIi338 d. Hot leg Recire. d. Closed :
- e. TNI173A e. RHR Pumo Discharge e. Cpen /
f $NI1788 f. RHR Pume Discharge f. Open g 7 nil 008 g. SI Pumo RWS7 Suction g. Open '
- h. TFW27A h. RHR/RWST Suction n. C;en z'
- i. VNI147A f. SI Pumo Mini flow i. Cpen ,. -
s' L4ayW - b. c'//AtWleatvEnce per ,
/
A 1. Verif 1 ping is.' . of natar by vent 4Tig /[ , jf'yfilg d . .ne ~'"l ' ~ ""G'}"" f" 5 Y 2
" /
ac /als m al, power opedted,
/ -
ujcestic) f i .np.fi 'fi ncf* pat th t locked, eff6d,or
~~
is ifervise in c 1 n_f-ts ce ct positi e c Sy sual- ct* whic fies that ,o de (rags, ras 41 ng . d.) i , esent in th on cme. w 'ch could..be,/ tr s ed t t ce nment sump ca re riction of- tbeV
~
ei
- p. A ' cti s CCA conditio ,, ,Dr v Ae erf ., e d- ' ual ijispectionphall/
y t- ',/ / accessible ar / / Fo -6'f the contai nt p rJ e ablishi
NMENTINTEGRIf'and 'M l 2./ f the areas a cted w n conta ..ent at +
eacn cc t'ai t entr' when CC ' .NMENT f ca co j th n of,isest011sned}
- d. At least e ri nths .
/
- 1. 'erif n a oma*' is a #d in lack actionfo a '
sys r Reac+ r oo nt Sy em when the Re ct oo! ant S em j ure is we " 0 ps
) '
( w/ J \ l McGUIRE - UNIT 1 3/4 5-g 9 a s jug 1901 W,VZ7~ 2 -
V -
.- r' EMERGENCY,CbRE C001.INd SYSTEMS
./,,,/ ,/ ,
bRVElLLANCE RE01]IREMENJ5-(-Ocndi ed) f
.y ., "
i 'Y'-
~. 2+-4t=Teast.occrper-18-montar:
M/7 " ' ,' Boron Injection Safety Injection
- ,. ,,;.7, / Throttle Valves ,
l Throttle Valves }
\
/EA'. Valve Number Valve Nutrber
/
#7[' .., S ):
/ l. -]NI-480 1. sNI-488
( A " j.. c 2. $NI481 k
- 2. JNI-489
= /
- 3. 2NI-a82 3. .INI-490 j
( ~ 4 gNI-483 4 JNI-491
, l. i . 3y ?e##"*4 g ' #10 ;6;ause test., during_,.s h ( #n1
,1 o _ o, n s
~
~.y::-g2 g.g;ccy w3j3,gg.<g%igom 7 l s a n~$ >= F *TicRnd=verregimyt:TatC
' C/ D s _ =- recsepi ft ..so r r . }_ p.' '= "g.i - -mng pumd lines,.with,a V Z,. '^ 7 ' singj e'$urs..
'^ '
( -g2" r' / ., a i . om of
- jection ' .e fk . es, exclucing th y l
w- .. rW'fl rate grea - . nan or equal :o ' .,pTn/
.f /'
b) h
/ ,/ .
al) - w rate 1 'tgan or eqtal,*J1.554 gpm. -
'f a) ,
hi
- s. .,
f .f.,r,"Js'gr
, terA, st -
th f(quil ,to 462,gpm,
,,4,
a '
/ ,- ./ ,/ , . .: .
7' , 1 pcip f a rah'i b) T Iess tNanor , I
- 3. ,o-3
,Ttie se ftheinje[tionline
,.s . , s}e,qu'ai, p_y a) tiw rates s grea [ han or
, f,.'equaV 3975spm./f. u-
/, ,
l'
/
.n.
(d i h i . l \ g,m r- ra v McGtjlRE - l' HIT 1 g$% wwr2. , ~
.g . _ .. . .. m- ~ ~~ - --~. n .: n-.. ... .
=L-
l , --- 1 4 g .- EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- e. At'least once per 18 months, during shutdown, by:
, , 1. Verifying th. each automatic valve in the flow path actuates !. to its correct position on ffafety Injection aettseti- =d ( .s-)
--d'- -
- ' - - . 7,, . /
test si l a Ce,,n~i%sor.oot Camp t?hirca/<sn~en ; te s ? gnalersyia c /.
- 2. Verifying that each of the fo' lowing puaps start automatically uoan receipt of a safety injection actuation test signal:
a) Centrifugal charging pump b) Safety injection pump c) Residual heat removal pump f
- f. By verifying that each of tne following~pumos develops *ne indicatec cischarge pressure on recirculation flow when tested pursuant to Specification 4.0.5:
; 1. Centrifugal charging pumo .1 O'Y psig
- 2. Safety Injection pump 1 /A ? / psig
- 3. Residual heat removal pump 1 /0 6~ psig i e
- g. By verifying the correct position of each electrical and/or mechanical position.stop for the following ECCS throttle valves:
- 1. Within 4 hours following completion of each valve stroking operation or maintenance on the valve when the ECCS subsystems are required to be OPERABLE.
- 2. At least once per 18 months.
~m N' 'RPSI System LPSI System - N
/, r 5 *j' valve M er Valve Number \,
fg vic & i - '
- a. a.
flg b. b. \ y~'
) i 7gy s- E c; 3.
N j W-STS 3/4 5-5 . NOV 2 01980 l _. - . . . . . . .
EMERGENCY CORE CCOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- h. By performing a flow balance test, during shutdown, following com-pletion of modifications to the ECCS subsystems tnat alter the subsystem flow characteristics and verifying that:
- 1. For centrifugal charging pump lines, with a single pump running:
a) The sum of the injection line flow rates, excluding the hignest flow rate, is greater than or equal to 3+E gpm, ana
- l b) The total pump flow rate is less than or equal to N
) gpm.
- 2. For safety injection pump lines, with a single pump running:
a) The sum of the injection line flow rates, excluding the highest flow rate, is greater than or equal to "e 4 gpm, anc b) The total pump flow rate is less than or equal to H I gpm.
- 3. For residual heat removal puma lines, with a single pump ,
runni.1g, the sum of the infection line flow rates is greater than or equal to397J~ gpm. l l l l O
'f-STS 3/4 5-6 NOV 2 1931
\- EMERGENCY CORE COOLING SYSTEMS 3/4.5.3 ECCS SUBSYSTEMS - T, < 350*F LIMITING CONDITION FOR OPERATION 3.5.3 As a minimum, one ECCS subsystem comprised of tne following shall be
! OPERABLE:
- a. One OPERABLE centrifugal charging pump,#
- b. One OPERA 8LE residual heat removal heat exchanger,
- c. One OPERABLE residual heat removal pump, and
- d. An OPERABLE flow path capable of taking suction from the refueling water storage tank upon being manually realigned and transferring suction to the containment sump during the recirculation phase of operation.
APPLICABILITY: MODE 4. ACTION:
- a. With no ECCS subsystem OPERABLE because of the inoperability of either the centrifugal charging pump or tne flow path from the refueling water storage tank, restore at least one ECCS subsystem to OPERABLE status within 1 nour or be in COLD SHUTDOWN within the next 20 hours.
- b. With no ECCS subsystem OPERABLE because of the inoperability of either the residual heat removal heat exchanger or resicual heat removal pump, restore at least one ECCS subsystem to OPERABLE status or maintain the Reactor Coolant System T**9 less than 350*F by use of alternate heat removal methods.
! c. In the event the ECCS is actuated and' injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describ-ing the circumstances of the actuation and the total accumulated actuation cycles to date. The currer,t value of the usage factor for each affected safety injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70. i
# A maximum of one centrifugal charging pump and one safety injection pump shall be OPERABLE whenever the temperature of one or more of the RCS cold legs is less than or equal to (4969'F.
O 3cc W-STS 3/4 5-7 yay 1 3 7ggg l
. - - - = . . . -. - - - . . . .
l I EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REGUIREMENTS l 4.5.3.1 The ECCS subsystem shall be demonstrated CPERABLE per the applicable Surveillance Requirements of 4.5.2. 4.5.3.2 All charging pumps and safety injection pumps, except the above required OPERABLE pumps, shall be demonstrated inoperable at least once per 12 temperature of one or mora of the RCS cold legs is less hours than orwhenever equal to I (ht,N&)*F by verifying that the motor circuit breakers have been removed from their electrical power supply circuitsy er Ay n ei J y, ;,y 4, a 4> < hey 4 ench ,rw m,o has h en is c hfes{ fit s,,
,St <* (e o. hr (crN) ! by bs** by 'I Y t'd e' Sf +sys s
/Er/akk y.ith,, wi rA f*-% '. . r re ass % ./ /rcir, &d e. yar /yc $/vs >; ee,,
9 O
'd-STS 3/4 5-8 h!AY 151978
O' EMERGENCY CORE COOLING SYSTEMS 3/4.5.4 BORON INJECTION SYSTEM BORON INJECTION TANK LIMITING CCNDITION FOR OPERATION 3.5.4.1 The boron injection tank shall be OPERABLE with: o *1"ry/ sM if/M
- a. AJcontained borated water volume of 5:tu:;. MM gallons, 4ccc % NC
- b. A boron concentration of between -20,00^ and -29799& ppm, and
' c.ime.. ;; : tier t::;;. etw, e ;f ' 4 5*c APPLICABILITY: MODES 1, 2 and 3. uN2 r / evt r ACTION:
With the baron injection tank inoperable, restore the tank to OPERABLE status within 1 hour or be in HOT STANOBY and borated to a SHUTDOWN MARGIN equivalent 1 to 1% delta k/k at 200*F within the next 6 hours; restore the tank to OPERABLE status within the next 7 days or be in HOT SHUTDOWN within the next 12 hours. SURVEILLANCE REOUIREMENTS 4.5.4.1 The boron injection tank shall be demonstrated OPERABLE by:
- a. Verifying the contained barated water volume at least once per 7 days,
- b. Verifying the boron concentration of the water in the tank at least once per 7 days, and
- 0. - W rifvink t M -wet:r te..,,s eture at=least-enc: p= 7dhwse O
W-STS 3/4 5-9 APR 15 Egg
EMERGENCY CORE COOLING SYSTEMS TRACING , LIMITING ONDITION FOR OPERATION 3.5.4.2 At leas
- two independent channels of heat tracing spa ll/ ce OPERA 8LE for the boron inje tion tank and for the heat traced portions of the associ-ated flow paths.
APPLICABILITY: MODES i, 2 and 3. ACTION: With only one channel of Peat racing on either he baron injection tank or on the heat traced portion of an as'sociated flow tn OPERABLE, operation may continue for up to 30 days provided the tank nd flow path temoeratures are verified to be greater than or equal \to (14 F at least once per 8 hours; otherwise, be in at least HOT STANDBYNwit n 6 nours and in HOT SHUTCOWN within the following 6 hours. \ 9 SURVEILLANCE RECUIREMENTS x 4.5.4.2 Each heat tr ing channel for the boron inject' son tank and associated flow path shall be d onstrated OPERABLE: \
\
l a. At leas onceper31daysbyenergizir.geacnhea(tracingchannel, and \ [ b. A leastonceper24hoursbyverifyingthetanka\n flow path l emperatures to be greater than or equal to (145)*F. The tank temperature shall be determined by measurement. The 1(low path temoerature shall be determined by either measurement eq recircula-tion flow until establishment of equilibrium temperature ( within the tank. \ g W-STS g SEP 15 95
EMERGENCY CORE COOLING SYSTEMS 3/4.5.5 REFUELING WATER STORAGE TANK 1 LIMITING CONDITION FOR OPERATION _ l l 3.5.5 The refueling water storage tank (RWST) shall be OPERABLE with: ar A .v r 37L / :c
- a. A contained barated water volume of b M 1 gt gallons,
- b. A boron concentration of between (2000) and (2100) ppm of baron, and 70 .
- c. A minimum water temperature of (36)*F.
APPLICABILITY: MODES 1, 2, 3 and 4. 1 ACTION: l Witn the refueling water storage tank inoperable, restore the tank to OPERABLE status within 1 hour or be in at least HOT STAND 8Y within 6 hours and in COLD SHUTDOWN within the following 30 hours. O SURVEILLANCE REOUIREMENTS 4.5.5 The RWST shall be demonstrated OPERABLE:
- a. At least once per 7 days by:
- 1. Verifying the contained borated water volume in the tank, and
- 2. Verifying the baron concentration of the water.
l b. At least once per 24 hours by verifying the RWST temperature when l the (outside) air temperature is less than M*F. 70 I l O l I tSTS 3/4 5' Xg , APR 151978 l - . . .
..w-u - -
v-- s-- ---a - e- me, , -,y- - w -y- -ee--+- ,- > c- -e. --
-e- - we-w ww w--r-=a. rp-e -e- - , -i-- " - < - - " - - -"
l SECTION 3/4,68 CCNTAINMENT SYSTEMS SPECIFICATIONS FOR WESTINGHOUSE ICE CONDENSER TYPE CONTAINMENTS O l l i i O
-w" * ------ - - - -
O 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained. APDLICABILITY: MODES 1, 2, 3, and 4. ACTION: Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within 1 hour or be in at least HOT STANDBY within tne next 6 hours and in COLD SHUTDOWN witnin the following 30 hours. SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
- a. At leas *, once per 31 days by verifying that all penetrations
- not capaolt: of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closer, by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in Table 3.6-2 of
( Specification 3.6.4.1.
- b. By verifying that each contain:nent air lock is OPERABLE,per Specification 3.6.1.3.
- c. After each closing of each penetration subject to Type B testing, except the containment air locks, if opened following a Type A or B test, by leak rate testing the seal with gas at P % psig M verifying that when the measured leakage rate for,these seals i(s p' ' p added to the leakage rates determined pursuant to Specifica-tion 4.6.1.2.d for all other Type B and C penetrations, the combined leakage rate is less than or equal to 0.60 L,.
I x Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed or otherwise secured in the closed position. These penetrations shall be verified closed during I each COLD SHUTDOWN except that such verification neec not be performed more often than once per 92 days. P ICE CONDENSER 3/4 6-1B MAR 181981
CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE ( LIMITING CONDITION FOR OPERATION
- 3. 6.1. 2 Containment leakage rates shall be limited to:
- a. An overall inte r ated leakage rate ofp f, Less than or equal to L containment air per 24 $o,u(0.20) percent 2 by weight of the rs at P, j(a,93 psig), y-
.ar ne f i ght,o f,t,he
.k6s$f$batga&r ccotument f Yperecuayye-Cg(Ofercent 24do<stsGt'k .rniduce ressurynAYP,f
#s#6T.
- b. for all A combined leakage penetrations and valves ratasubject of lesstothan TypeorBequal and Ctotests, 0.60 aL, hen pressur-ized to P,. ,
- c. for A allcombined penetrations bypass identified leakage rate of3.6-1 in Table less as than or eQJal containmen secondary to (0-h't) L, t bypass leakage paths when pressurized to P,.
APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: With either (a) the measured overall integrated containment leakage rate
- 0 75 '. -
' ' " ' - or (b) with the measured combined exceeding leakage rate0.75L*a:llpenetr$tionsandvalvessubjecttoTypesBandCtests for exceeding 0.60 L , or (c) with the combined bypass leakage rate exceeding c'.0 7 QW L , resto@e the overall integrated leakage rate to less than or equal to 0.75 & cr i;;; ther. cr ewel te 0.75 L , es sppTtrah and the combined leakage r$te for all penetrations and valvIs subject to Type B and C tests to less than or equal to 0.60 L , and the combined bypass leakage rate to less than or equal temperatur: aboveto200*F. M (L, p@ior p.g to7 increasing the Reactor Coolant System SURVEILLANCE REQUIREMENTS ,
- 4. 6.1. 2 The containment leakage rates shall be demonstrated at the follow ng i test schedule and shall be determined in conformance with the criteria speci-fied in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-(1972)p cy- fje n,ais pfef me f/st /';
e d-ICE CONDENSER 3/4 6-28 MAY 151980
CONTAINMENT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued)
- a. Three Type A terts (Overall Integrated Containment Leakage Rate) sna11 be conducted at 40 : 10 month intervals during shutcown at efs.a} ~
~
;t '. ('O p f d during eacn 10 year service pericd. QThe (24'psig) third test of sach set shall be conducted during the shutdown for the 10 year plant fi1 service inspection.
- b. If any periodic Type A test fails to meet h 0.75 L c'"'
the test schedule for suosequent Type A tests shall be feviewed and approved by the Commission. If two consecutive Type A tests fail to meet N 0.75 L c- J.75 L, a Type A test shall be performed at least every 18 mon!hs until tGo consecutive Type A tests meet N 0.75 L resume 8.or ' M ' , at wnicn time the aoove test schedule may be
- c. The accuracy of each Type A test snall be verified by a supplemental test wnich:
- 1. Confirms the accuracy of the Type A test by verifying that tne
( m difference between supolemental and Type A test data is within l 0.25 L,, m 0.2 % ,
- 2. Has a duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test.
- 3. Requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to be l equivalent to at least 25 percent of the total measured leakage
! at P a f(47JF psig) c y (25 p ig). fp. g
- d. Type B and C tests shall be conducted with gas at P 26 psig) at intervals no greater than 24 months texcept for test $ (involving:
- 1. Air 1ocks, s ' ~ " " ' '
",
- p,_
d :%',%p., . +,. ..w, t, A. > - rn d
.L k t-p./y 1.eya :; a > > a ~ M *u '
, .n.; s*
,C L - ';n:triticM _;i.; ;;.d nu0 L1,,,.m ,; -;-- '- '.; ;j;;;,i.;, :nd
-- m . . , m . ,. ; ;. . = . Mh i d '- r ; -;; _ l ,g ;; .
l 0.07 l
- e. Thecombined[bypassleakagerateshallbedeterminedtobelessthan or equal to Ifr44ik) L by applicable Type B and C tests at least once per 24 months except,for penetrations which are not individually testable; penetrations not individually testable shall be determined to have no detectable leakage when tested with soap bubbles while the (26 psig) during each Type A test.
O containment is pressurized to P,/$$ b W-ICE CONDENSER 3/4 6-38 MAY ' 5 1930
CONTAINMENT SYSTEMS' SURVEILLANCE REQUIREMENTS (Continued)
- f. Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.3.
-gh,m%p T if pripdic t are,p f reg'fpr--penetr1tions continuousl' 4 oni.taf,e 60 e ai,twent' tition',94Tve 6d-Ch'annet'Qeld P ' . -
~4's6i(2 4' y 'y PERABLy. p'er -
31iti'c. egufremen ,4.o.17 g avid,e, th //,ss'.(ms'
/ -
[ FLeakage frdm plat 9fr valves,that
.sys, tem sa'y.be'excludeg,-sybject + are wi.t seaofi1To of-Kppe s[tr'fluidJora xJ / ,
, seal Section Irl.C.3, en dete ' ,1 'J1,e; mbined eakage te pr:d, i~fe_d{ ,.
the seal ,syst and,va -pres ' zed,t'oIatle f <l 1D' [ ( G f' y J- > ps.h,d ' e sed
~
'apact is adecuate to ntain sy}15eK #
pressure for at east <30' days.' //
. -it.Mype'I, tests p' g Fa't ' plo y<cntint:tT6s'deskaj;erma'nk:ot :"
fngisirstimc ' ,bd', ~, ZD-psf @atji'nterillh"'n1greaEar than'6nc per vs. ' f- /. 5 The provisions of Specification 4.0.2 are not applicable. { y n. y.., . j h. .. n .e..ic A laa/ j'/y h 'A "'s " ' "'" IIP "' l : . ,,hi,h ,, ,/ ycn a fra Sn.r 3c hvvn rAc c '" h' " "' ' ~ f A" i Ab7 I s,/ 94e airn v/w s s/r., // i, w n fv n' /c* tA ~- "" " /"' * *'" Mr9 y,c y A ye.c / .c . fe//c ws**y ce>>yr/* fitn <' f **"' b 9,^' A p,p , tA r spaae. Je hm <ie A / .r/-f? A e //' " a3g, n,j/y .chsr// )< cudje chd h a low fra ssurc h'Y ,_ A
,,p y s ,r iy 7'c c/e a a a /rv 7 k 7'h *
/ &ye/ & *!
/ //c.. v.
t.est le a /c ry.r. re fa s sA'r H A< c r /c wh7%f 4JOyr
), , ,1 y </ A R 4 7% va/w.: < , Err. ,-
ejse <w,/ a'a rt, cwe r7%d H 7'c cehda br A i' < s / air r/ysi s SAo# Ae j>ee fern,e / in e a sura.sn e,,7 4 - sy.s h n, in f<fral*W h akef e i G
~
W-ICE CONDENSER 3/4 6-48 gg 6 1981
O U i
._I Alli E 3. ti- 1 N
g StCotiDARY Col 41 Alt 4HElli BYPASS tFAKAGE PAlllS M pet 1EIRATION TEST f a tillHBER SERVICf REL EASE t oC Allull lYPE c (5
) H216 Pressurizer Relief Iank Makeup Auxiliary fluilding lype C I
l k["~' 1 H212 flitrogen to Pressurizer Relier lank Auxiliary liuilding lype C b H259 Reactor Hateup Wates lank to liv k System Auxiliary building lype C ~_ H373 Ice Condenser Glycol in Auxiliary Unilding lype C H3/2 Ice Condenser Glycol Out Auxilicry Huilding Type C z.k H330 Nitrogen to Accumulators Auxiliaiy fluilding lype C g R u H321 Safety injection Test Line Auxiliary tsuilding Type C yi H348 Upper llead Injection lest line Auxili.siy building lype C lW
? H374 Containment I~loor Sump Incore Instrument Sump Discharge Auxilia y lluilding Type C H360 Reactor Coolant Drain Tank Gas Space to Waste Gas System Auxiliary Building lype C H375 Reactor Coolant Drain Tant lleat Exchanger Discharge Auxiliary Building lype C H356 Equipment Decontamisiation Auxiliary lluilding lype C H235 Pressurizer Sample Auxiliony Building lype C H309 Reactor Coolant flot leg Sample Auxiliary Unilding lype C H322 Component Cooling to Component Cooling Drain Tasik Auxiliary fluilding Type C e @ *
(s) D Ng' 4 1Autt 3.6-1 c SEC0illlAIU CONIAlliHENT BYPA% I EAKAGF PAlll5 lE PENEIRATION TEST e NUHilER SERVICE RE t f. A_S_E _10_0A1_1_0.N TYPE Huclear Service Water to Heactor h3 H307 Coolant Pump Auxiliary Building Type C 3[ Ja H315 Nuclear Service Water From Heactor ! Coolant Pump Auxiliary Liuilding Type C H213 Incore Instrumentation Room Purge in Auxiliary 11uilding Type C M138 Incore Instrumentation Room Purge ! Out Auxiliary Building Type C H367 Upper Compartment Purge Inlet Auxiliary lluilding lype C H454 Upper Compartment Purge Inlet Auxiliary Building Type C 4 N Q H357 Lower Compartment Purge inlet Auxiliaiy finilding Type C M456 tower Compartment Purge Inlet Auxiliary Huilding lype C H368 Containment Piirge Exliaust Auxiliai y tiuilding Type C H4SS Containment Purge Exliaust Auxiliary fluilding Type C Mll9 Containment Purge Exhaust Auxiliary finilding Type C H337 Demineralized Water Auxiliar y thailding lype C H240 Containment Ventilation Cooling Water In lurliiue ilu s Iding Type C H385 Contaisunent Ventilationi Cooland Water in lurtiine hullding lype C
h 0 o O (a U I Allll~ 3. 6- 1 SECONDARY C0fdIAINMfN1 ilYPASS tlAKAGl PAlll$ r$ PENE1 Hall 0N TESI e NUMBER SERVICE Rtl[ASL 10CAIION lYPE SC ME H390 Containment Ventilation Cooling b" Water Out Turbine unilding Type C 1" g H279 Containment Ventilation Cooling Water Out luibine UniIding Type C H220 instrument Air Auxiliary fluilding Type C l H219 Station Air Auxiliary Building Type C e l H215 Breathin0 Air Auxiliary fluilding Type C H378 Containment Sample Out
, Auxiliary Buildin0 lype C H325 Containment Sample In c e Auxiliary Building Type C i
8 H358 Refueling Cavity to RW Pump Auxiliary Building l O Type C
! H377 Refueling Cavity from RW Tank Auxiliary Building Type C H331 flydrogen Purge in Atmosphere Type C H326 RCP Hotor Drain lank Pump to Waste Oil Storage Auxiliary Building lype C H221 Containment Ventilation Units Condenser Drains to Condenser Drain Tank Auxiliary Building Type C H359 Instrument Air Auxiliary lluilding lype C
~
H386 Instrument Air Auxiliary Building Type C e e G ,
I I Allil 3.6-1 ) k SFC0tlDARY CONIAINMilli BYPASS L FAK/sGt PAlliS l 5 ' 7
\
l A PENEIRATION lEST ' HUMBER SERVICE REl l ASI 10CA110H lYPE C
-s H317 Instrument Air Auxiliary fluilding Type C $
! 1- H243 Containment Air Release Auxiliary 13uilding Type C s, ,i H384 Containment Air Addition Auxiliary Building Type C k ' H361 Reactor Coolant Pump Motor Oil Supply Auxiliary fluilding Type C ,s tu l H353 Fire Protection lleader Auxiliary fluilding Type C H376 Component Cooling Water to Auxiliary Building Type C s
, Reactor Coolant Drain Tank 2 lleat Exchanger b' (3 ,
~
! (, H355 Component Cooling Water from * ' Auxilia:y Buildinr Iype C
;) Reactor Coolant Draisi Tank 4 lleat Exchanger H3?'8 Component Cooling Water to Auxiliary Building Type C b
Reactor Vessel Support "4 s Coolers and RCP Coolers H320 Component Cooling Water from Auxiliary Building lype C Reactor Vessel Support Coolers and RCP Coolers Flued llead to Guard Pipe Atwosphere, or Welds on all llot Auxiliary lluilding, Penetrations or Itu bine fluilding
- Equipment flatch Atmosphere lype C
Pursuant to Specification 4.6.1.2.e.
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CONTAINMENT SYSTEMS CONTAINMENT AIR LOCXS LIMITING CONDITION FOR OPERATION 3.6.1.3 Each containment air lock shall be OPERA 8LE with:
- a. Both doors closed except when the air lock is being used for normal i
I transit entry and exist througn the containment, then at least one air lock door shall be closed, and o. An overall air lock leakage rate of less than or aqual to 0.05 L, at P, H. ?W psig). APPLICABILITY: MODES 1, 2, 3 and 4. ACTION:
- a. With one containment air lock door inoperacle:
- 1. Maintain at least the OPERABLE air lock door closed and either restore the inoperable air lock door to OPERABLE status within 24 hours or lock the OPERABLE air lock door closed.
- 2. Operation may then continue until performanca of the next j required overall air lock leakage test provided that the OPERABLE l
air lock door is verified to be locked closed at least once per 31 days.
- 3. Otherwise, be in at least HOT STAND 8Y within the next 6 hours and in COLD SHUTD0hN within the following 30 hours. ,,
l l 4. The provisions of Specification 3.0.4 are not applicable. l l
- b. With the containment air lock inoperable, except as the result of an l inoperable air lock door, maintain at least one air lock door closed; I
restore the inoperable air lock to OPERABLE status within 24 hours or be in at least HOT STAN08Y within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. O W-ICE CONDENSER 3/4 6-68 MAY 15 ic80
CONTAINMENT SYSTEMS f g\ V SURVEILLANCE REQUIREMENTS (Continued) l, ;, 3 :. = & ; '
- I A >i~*N 4' dc~ n a'r'= n' ??~~'?? M -~-
a. 7 ,r
- js After each opening, except when the airlock is being used for ^
s, Ic multiple entries, then at least once per 72 hours by verifying that p' u the seal leakage is less than or equal to 0.01 L as determirec by
' precision flow measurement when measured for at feast 30 seconds with the volume between the seals at a constant pressure of .-
l'.< [: & ,*
~,
14.8 psig. " !/ or,46 4stablish pff,CONTAJNMENT.riNTEyRITJrif p .en 6CONTA1HME$1NTJCET7/wa,54 tot .rpqui red, ,and 6 mentk, by,2cnduc'ti ,an ov 'a l '1V. s ce/ er , J ,e ed les a s%' t// g"(g(4X 93 s'i T,anp6y'fv rffy)ng that'}dd(o/oc is witMn it.s I rmt ( v atI i'r 1 I.atf$'r,g,;rt4. g
,' c. At least once per 6 months by verifying that only one door in each N
~ ~~ ,
air lock can be opened at a time. d. At least once per 6 months by conoucting a pressure test to verify x door seal integrity, with a measured leak rate of less than or equal ,.,', to 14.95 sccm. '
-t
\ ?)f S Cp - f Y c' 0 pe 3/Y 6 -?B l
l s m - . Mfhehroisid S on 4.0.2 ar ap McGUIRE - UNIT 1 U A . / .1. 3/4 6-7 7 8 (Ie4,-il '
O CONTAINMENT SYSTEMS
!URVEILLANCE REOUIREMENTS
- 4.6.1.3 Each containment air lock shall be oemonstrated OPERABLE:
/ [" ,aP?.WiNin'72 hdurs following eac(closJti[, ex8pt when the aN' lock is' l
g,, , r ' fbein Aised for multiple entyfes,..then.at ) east.once,per 72 hours., by
*yer,r yjn .cetectable. seal eakage byf ressere, decay when, trJe' /
N yelume b een the door deal itpressu ied,to'greag,than Ar eq0al7ov, T20 psig) for at least is minutes.
- b. By conducting overall air lack leakage tests at not less than P , ),
(20 psig), and verifying the overall air lock leakage rate is within - its limit:
- 1. At least once per 6 montns,# and
- 2. Prior to establishing CONTAINMENT INTEGRITY wnen maintenance .,
has been performed on the air lock that could affect the air ,. lock sealing capability." . _ _ _ . _. _/ c'. At lea [t $crp5r '6 monthsiy verifying that only'0Fdoor jn each[.. ~' D' air ich-t:an be topenid at a GireT t/ LX The provisions of Specification 4.0.2 are not applicable.
- Exemption to Appendix J of 10 CFR 50.
O . W-ICE CONDENSER 3/4 6-7B SEP 151981 h _ _ - _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ ___
x U NTAINMENT SYSTEMS 9 CO INMENT ISOLATION VALVE AND CHANNEL WELD PRESSURIZATION SYSTEMS (OPTI dAL) LIMIT CONDITION FOR OPERATION ,
- 3. 6.1. 4 The c\ontainment isolation valve and channel weld pr surization systems shall be' ERABLE.
APPLICAPILITY: MODE 1, 2, 3 and 4. ACTION: With the containment isolatico valve or chann weld pressurization system inoperable, restore the inoper'able system t/0PERABLE status within 7 days or be in at least HOT STAN08Y withi' he nex' / 6 hours and in COLD SHUTD0%N within the following 30 hours. SLRVEILLANCE REOUIREMENT s
'N 4.6.1.4.1 The cc ainment isolation valve pressurization system shall be demonstrated OPJ. BLE at least once per 31 days by verifylng that the system is pressurizejrto capacity to aintaingreater than or equal system pressure for at to 1.10 P,30 days.(22 psig)\and has adequa least 4.6.1.4 The containment channel weld pressurization system shall de demon-l strat OPERABLE at least once per 31 days by verifying that the syste'Qs pre urized to greater than or equal to P (20 psig) and has adequate cap 'ty t maintainsystempressureforatleast30 days. , /
AAN 1 1 l 9 l l P ICE CONDENSER [3/4 OCT 1 1975
- .._a. .- -- -
---._._- ^-- - -
J CONTAINMENT SYSTEMS ! INTERNAL PRESSURE LIMITING CONDITION FOR OPERATION
+
- 3. 6.1.Ir" Primary containment internal pressure shall oe maintained between
- (. 7 and -st 3 psig.
APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: With the containment internal pressure outside of the limits above, restore the internal pressure to within the limits within 1 hour or be in at least HOT STAND 8Y within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
"'!RVEILLANCE REQUIREMENTS O .
4.6.1.# The primary containment internal pressure shall be determined to within the limits at least once per 12 hours. l l O W-ICE CONDENSER
~
3/4 6 .98- OCT I 1975 83
,____..*-,,y .-
CONTAINMENT SYSTEMS I'4 TEMPERATURE q- , LIMlIINGCONDITIONFOROPERATION 3.6.1.6 imary containment average air temperature shall be a intained: ' N
- a. Bebeen 75 and /e*o *F in the containment upper compartment, and b.
k Betweb /#0 and /.2c 'F in the containment low r compartment.
/
APPLICABILITY: MC ES 1, 2, 3 and 4 ACTION: With the containment average air temperature not,' conforming to the above
/
limits, restore the air temp'erature to within the limits within 3 nours or ce in at least HOT STANOBY withto the next 6 hours and in COLD SHUT 00WN within the following 30 hours.
\\
/
SURVEILLANCE REQUIREMENTS \/
/\
4.6.1.6.1 The primary containment/upper compartment average air temocrature shall be the arithmetical avera e of the temperatures at the follcwing locations: N Location
- a. x
- h. / N
- c. / 's N
4.6.1.6.2 The p mary containment lower compartment average air T.emperature shall be the ar' hmetical average of the temperatures at the follo' wing locations: Location
'\\
s i
- a. i
- b. ! \
\
C. - 4f .1.6.3 The primary containmeat average air temperatures shall be determined at least once per 24 hours. ftj G rC G W-ICE CONDENSER J24;6-108- JUL 151979 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - - - - - - - )
l
/m -
(J i CONTAINMENT SYSTEMS AIR TEMPERATURE LIMITING CONDITION FOR OPERATION 3.6.1.5 Primary containment average air temperature sna11 be maintained: 73~
- a. bet'een J6*F" and 100*F in the containment upper compartment, and
- b. between 100*F* and 120*F in the containment lower compartment.
APDLICABILITY: MODES 1, 2, 3 and 4 ACTICN: With the containment average air temperature not conforming to the above limits, restore the air temoerature to within the limits within 3 hours or be in at least HOT STANCBY within the next 6 hours and in COLD SHUTCCWN wi hin the following 30 hours. SURVEILLANCE REQUIREMENTS R V 4.5.1.5.1 The crimary containment upper compartment average air tem::erature shall oe the weighted average ** of all amoient air temperature monitoring stations located in the upper ccmpartment. As a minimu:a, temperature readings will be obtained at least once per 24 hours frem the following locatfens: Location
- a. Elev. 826' at the inlet of upper containment ventilation Unit 1A.
- b. Elev. 326' at the inlet of upper containment ventilation Unit 18.
I c. Elev. 826' at the inlet of upper containment ventilation Unit IC.
- d. Elev. 826' at the inlet of upper containment ventilation Unit 10.
l
" Lower limit may be reduced to 60*F in MODE 2, 3 and 4.
j ""The weighted average is the sum of each temperature multiplied by its respective containment volume fraction. In the event of inoperable temoera-ture sensor (s), tne weighted average shall be taken as the reduced total divided by one minus the volume fraction represented by the sensor (s) out of service. McGUIRE - UNIT 1 3/4 6-Jr W Wi~7' > TE
^
_ ___.c -
. .__ . __..._.z.__._.-...- . _ . _ . . . . -
_ _ - - - - ~ , CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.6.1.5.2 The primary containment lower compartment average air temperature shall be the weighted averaged of all ambient air temperature monitoring stations located in the lower compartment. As a minimum, temperature readings will be obtained at least once per 24 hours from the following locations: Location
- a. Elev. 745' at the inlet of lower containment ventilation Unit 1A.
- b. Elev. 745' at the inlet of lower containment ventilation Unit 18.
- c. Elev. 745' at the inlet of lower containment ventilation Unit 1C.
- d. Elev. 745' at the inlet of lower containment ventilation Unit 10.
O :
"The weigntec average is the sura of each temperature multiplied by its respective containment volume fraction. In the event of inoperable tempera-ture sensor (s), the weighted average shall be taken as the reduced total divided by one minus the volume fraction represented by the sensor (s) out of service.
. ~.
( :A McGUIRE - UNIT 1 3/4 6- W'
//M27 L /d //
muummmmmm.mm ia umhe sum
h 1 i '
, CCNTAINMENT SYSTEMS
- CONTAINMENT VESSEL STRUCTURAL INTEGRITY LIMITING CONDITIO'N FOR OPERATION l 3.6.1.9 The structural integrity of the containment vessel shall be maintained at a level consistent with the acceptance criteria in Specification 4.5.17 ,
. APPLICABILITY: MODES 1, 2, 3 and 4
! ACTION:
! With the structural integrity of the containment vessel not conforming to the above requirements, restore the structural integrity to within the limits
- prior to increasing the Reactor Coolant System temperature above 200'F.
f SURVEILLANCE REQUIREMENTS _
- 4. 6.1. it The structural integrity of the containment vessel shall be determined during the shutdown for each Type A containment leakage rate test (reference Specification 4.6.1.2) by a visual inspection of the exposed accessible interior
- and exterior surfaces of the vessel. This inspection shall be performed prior to the Type A containment leakage rate test to verify no apparent changes in
; appearance of the surfaces or other abnormal degradation. Any abnormal degra-j dation of the containment vessel detected during the above required inspec-tions shall be reported to the Commission pursuant to Specification 6.9.1.
4 l I !O l l W-ICE CONDENSER - 3/4 6-118 DEC 15 578 l
i CONTAINMENT SYSTEMS _ SHIELD BUILDING STRUCTURAL INTEGRITY , LIMITING CONDITION FOR OPERATION I f%: a 15 a-3.6.1.S' The structural integrity of the :H:!d 6uilding shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.$" 7 APPLICA8ILITY: MODES 1, 2, 3 and 4. ACTION:
,G u 7t-With the structural integrity of the :H :!d Building not conforming to the above requirements, restore the structural integrity to within the limits prior to increasing the Reactor Coolant System temperature above 200*F.
SURVEILLANCE REOUIREMENTS l 7 f.:a y,- 4.6.1.f The structural integrity of the sM444 Building shall be determined during the shutdown for each Type A containment leakage rate test (reference Specification 4.6.1.2) by a vgagi,nspection of the exposed accessible interior and exterior surfaces of the .. .E._ building and verifying no apparent changes in appearance of the concret surfaces or other abnormal degradation. Any t abnormal degradation of the building detected during the above required i inspections shall be reported to the Commission pursuant to Specification 6.9.1. l l l l l O l PICECONDENSER 3/4 6-123 CEC 5 E9 l
7 _
, x
, ~
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/
C_0NTAINMENT SYSTEMS ~ ,
, _ AIR CLEANUP SYSTEF 4
' ~
' LIMITING CONDITION FOff OPERATION
^
,?
, go;,a C ,, A% A:.,
3.6.1.5 Two indepene nt sh!:P. building 4 r--c.leanup systems shall be OPERABLE. APPLICA8TLI]: MODES 1, 2, 3 and 4. .
- /. .
ACTION: -
- rnisw h c y . n 5 % .4 :e,i ,
- With one- 2 kid .'. i'4 b p & :10 = system inoperao' le, restore the inoperable syrtem to OPERA 8LE status within 7 days or be in at least HOT STAN08Y within ,
tne next 6 hours and in COLD SHUTDOWN within the following 30 hours. '
~
SURVEILLANCE REQUIREMENTS - 3 cuima /tr 3 w.nh% N r ~ ^
, 4.6.1.# Each di: M M kg 9 Q anup systen shall be demonstrated OPERABLE: ~
a( At least once per 31 days on a STAGGERED TEST BASIS by initiating, , from the control room, flow through the HEPA filters and charcoal ' adsorbers and verifying that the3ystem operates for at least 10
~~
~
hours wi o " *' ?
- A " "' ' ' * '? "" "'N '
- s.r ari*th .t the n heaters th, ear 44 7e%'"
e,- ap.a/ 9-4 n.'s A .- . h 4- m is
- ty = = t
- b. At least once per 18'molitts_ or (1) after.any structural maintenance on the !iEPA filter or charcoal adsorber housings, or (2) fc11owing '
painting, fire or chemical release in any ventiTation zone comeuni-l 1
'ating with the system by:
that W1 'y3tes operating at a flow-rate-of _.-
-Y['.3rif. -cfir app' ' sting. througN'tWe'HEPA
% toWWass flow of ,f.11
~ and l recal adsorb,e p, system to the l +
iJ1 tyitent(ine~luding-leakage through4t system diverting i ve Wes, is'le TPor w sh
- Wsted -
or g @ i-t /- by ,4 del , d sys y ,heT the diverti y tw.e t,> Verifying that the .c"*eenup system satisfies the in place testing
/, &
acceptance criteria and uses the test procedures of Regulatory Positions C.S.a. C.5.c and C.5.d of Regulatory Guide 1.52 Revision 2, March .1978,yand the system f!cw rate is W c,fa 's 10%. (a m ar fer Hua. p vv.~a w ef A N 5"I N81Cr;",,j,"hy , de & Verifying within 31 days after. removal that a laboratory ana. lysis of a representative carbon sample obtained in accordar.ce with
. Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, W-ICE CONDENSER 3/4 6-138 APR Ig g7,
- 'we tr w w ww>e ,e- ,-
l l l CONTAINMENT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.
- 4. Verifying a system flow rate of Scro efm 10% during system operation when tested in accordance with ANSI N510-1975.
- c. After every 720 hours of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of a repre- .
sentative carbon sample obtained in accordance with Regulatory Position C.6.b of Reculatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.
- d. At least once per 18 months by:
- 1. Verifying that the pressure drop across the combined HEPA
' filters and charcoal adsorber banks is less than (6) inches Water Gauge while operating the system at a flow rate of Tc" cfm : 10%.
- 2. Verifying that the system starts automatically on ad f containmd
/54te- # 4em isolation test signal (S f ), 5% e f cyces.fy)< / . M a+, cy.nn d
- 3. Verifying that the filter coolin bypass valves can be - w=';
opened.
-Jc ' y [ erifying hat ch tem aduc a nega ve pr re of
#~ I ( inu s .
- 5. Verifying that thejke*a#N t dissipate W.c : 6 4 kw when tested in accordance with ANSI N510-1975.
, e. After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to (99.95)%" of the DOP when they are tested in-place in accordance with ANSI N510-1975 while operating the system at a flow rate of
,fCC c cfm 10%.
l j f. After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 09.95% of a halogenated hydrocarbon refrigerant test gas whc- they are tested in place in accordance with ANSI N510-1975 while operating the system at a flow rate of 5't ot- cfm : 10%. 39 11 9 fi e l O W-ICE CONDENSER 3/4 6-148 MAY 15 fcE0 l l l
.. _ q (3
V ()- CONTAINMENT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) f
^
- f. jAfter ever,y 72kh'ours qf,' char, coal ,acsprber-operatjonIyerffyingf'J' W ^
/ within 3T. days aftergramovAl tha, ,,1 rjeary-anaipisof,ar,epr,e- ;
sentativVcarocad60lefobtah) - accordance htR6gyl'Epry ' -j-Position CA'V5f' Reg &1
/ *de '
/
d'/ , meets }he
'/of Rerq'u15y6oratafy/ ri ter}<5?As a for ,n,Mapen o
,1978
.6.a 978( /'f'* s, ,,sity - n l'/j/ W-le/
/
Q. h,
.ory,G&i
,/ / / f/
asltonce/pe $'montns. evi
,,/gi'Efp'ec.
.c. -
'% / *
, jf ',g, '
,, /
r 1/ ,.-Ve,rif j ./ d //,th[at, ag/ arcoal prescurp dfcp across tha-ccmoined HEPd rsp orber banxs is less-etra,n 6' inches uge
' </
,- 'opedt~ ng thejysten at -s ' flow-rsta>cf 800 ,,
m + 10*. . f ! / / / . / , s / Y /[' 27 ing,' tflat the -sy, stem starts 4utemaMc U1,'e('a -
.nment cent ri'j,8' iso ation y test S inU"'
~
~
P ' '" y '
/ a' 3.4 .Ver'.ying/t the'f
/
.. / /* }')#.-f-l' g(21*roffacactt9)"s-sele'ctrTc/'
N~~
/'
si coo'// 4-motor cae ated hppass valve cangeccene.. m
,S (O Verifying that each system produces a pressure equal to or more
# negative than -0.5 incnes W.G. in tne annulus within 23 seconds J' ~g , af ter a start signal and tnat this negative pressure <;ces to -
W -3.5 incnes W.G. within 53 seconds after tne start signal. - er,,e f Verifying that upon reaching a negative pressure of -3.5 incnes W.G. in the annulus, the system switches into its recirculation [/ypL ' mode of operation and that the time required for the annulus pressure to increase to -0.5 inches W.G. is greater than or
/
/
equal to 278 seconds. -- 5'.'- 1g t3a eheste'F f451
' 6 ,4 kw Gne' j
'e. /^ '*k*sWt -thir>L ^" "?"/
A . omo at 'tial a of-(,/ HE8 f tar-b /g 1 A fil hant emo ' at~er an 3r-ti;uar to
'j ,<99
- C P,yhe,D (h ' . , , ' ' (slace i 0- 75 e op a ' - .. e-#
efga6'4Tlh s - at . cate 00 fm
- f. Mt f ch compt [ts o ll-t,1a f /f l y vertfyin un' ' be' .c r o, .' ar' a)/apso[ber dsor r , eater than c [#' ' h'
/ e I ta
hep tfieyWa 95 'of- tyrl. a hydro fri cant tes,tQa operati ed ' sts.'i t" 1 f in ac ' J' wit 6I t:DO-19 wnile dy$l' w r .'qf' 000 c' /J' 0Y l ) I U v McGUIRE UNIT 1 3/4 6-)4 t/ NIT 2-
/1~f
-- . - . . - - - gT1 n
c' CONTAINMENT SYSTEMS CONTAINMENT VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.9 The purge supply and exhaust isolation valves for the lower compartment and instrument room of the containment shall be closed. Operation l with the purge supply or exhaust isolation valves for the upper compartment of l the containment open shall be limited to less than or equal to 90 hours per 365 days. APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: With one or more containment purge supply or exhaust isolation valves fcr the lower compartment or instrument room open or with one or more containment purge supply or exhaust isolation valves for the upper compartment open for more than 90 hours per 365 days, close the open valve (s) within one hour or be in at least HOT STANOBY within the next 6 hours and in COLD SHUT 00WN within the following 30 hours. p SURVEILLANCE REQUIREMENTS t 4.6.1.9.1 The purge supply and exhaust isolation valves for the lower compartment and instrument room of the containment shall be determined sealed closed at least once per 31 days. 4.6.1.9.2 The cumulative time that the purge supply or exhaust isolation valves Nr the upper compartment of the containment are open during the past 365 dea shall be determined at least once per 7 days. l l l l l I i t' l McGUIRE - UNIT 1 3/4 6 ,1T gg JUN 1981 . t/NT Y 2_ l _ _ _ _ --
1 I l
~
' CONTAINMENT SYSTEMS CONTAINMENT VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.10 .Th9 (42 inch) containment purge supply and exhaust isolation valves shall ce h ie'd closed. Coeration with the (8 inch) purge supply and/or exnaust isolation valves open should be limited to less than or equal to (90) hours per 365 days.
APPLICABILITY: MODES 1, 2. 3, and 4. ACTION: With the (42 inch) containment purge supoly and/or exhaust isolation valve (s) open, or with the (8 inen) ourge supply and/or exnaust i9olation valve (s) open for more than (90) hours per 365 days, close the open valve (s) within one nour or ce in at least HOT STANOBY within the next 6 hours and in COLD SHUTDOWN witnin the following 30 hours. 1 l O SURVEILLANCE REQUIREMENTS 4.6.1.10.1 The W i.2 )ccontainment purge supoly and exhaust isolation
'hi to be: O M"~*"'"". * "
&% 6a;1ninpa ->::fn s,40 valves s.,,;w 3e = ' W k' w"'
' " " *>Yrs'E',e</
h" *" Y ""
k he~
- a. Closed at least once per 24 nours.
l
- b. Sealed - closed at least once per 31 days.
4.6.1.10.2 The cumulative time that the W ' :') purge supply and exhaust isolation valves ave been open during the past 365 days shall be determined at least once pe 7 ys gs ,g g u,,fr,w. 7 4.6.1.10.3 ' At least once per 6 months on a STAGGERED TEST BASIS each sealed closed (42 inch) containment purge supply and exhaust isolation valve shall be demonstrated OPERABLE by verifying that the measured leakage rate is less than or/ equal to (0.05) L,.
/
4.6.p10.4 At least once per 3 months each (8 inch) containment purge supply and, exhaust isolation valve shall be demonstrated CDERABLE by verifying that the measured leakage rate is less than or equal to (0.05) L,. Scr-+- =ded-W-ICE CONDENSER p41jlsk gg g g 1931 l m -
-ev-
/gf A {
CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS } CONTAINMENT SPRAY SYSTEM (Credit taken for iodine removal) LIMITING CONDITION FOR OPERATION 3.6.2.1 Two indepencent containment spray systems shall be OPERABLE with each ! spray system capable of taking suction from the RWST and transferring suction to the containment sump. APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: With one containment spray system inoperable, restore the inoperable spray system to OPERABLE status within 72 hours or be in at least HOT STAN08Y within the next 6 hours; restore the inoperable spray system to OPERABLE status within the next 48 hours or be in COLD SHUTOOWN within the following 30 hours. SURVEILLANCE REOUIREMENTS 4.6.2.1 Each containment spray system shall be demonstrated OPERA 8LE:
- a. At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked sealed, or otherwise secured in position, is in its correct positon.
b By verifying, that on recirculation flow, each pump develops a discharge pressure of greater than or equal to /8f psig when tested pursuant to Specification 4.0.5.
- c. At least once per 18 months during shutdown, by:
- 1. Verifying that each automatic valve in the flow path actuates to its correct position on a test signal.
- 2. Verifying that each spray pump starts automatically on a test signal.
- d. At least once per 5 years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed.
O W-ICE CONDENSER 3/4 1s 2168 ' MAR 151978 9 \ L - __ _ _ _ _ _ _ _ . . . . _ . _ _
CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM (No credit taken for iodine removal) LIMITING CONDITION FOR OPERATION _ 3~.6.2.1 Two independent containment spray systems shall be OPERABLE with each spray system capable of taking suction from the RWST and transferring suction to the conteinment sump. APPLICABILITY: MODES 1, 2, 3 and 4. l ACTION:
- a. With one containment spray system inoperable and at least*(four) ;
containment cooling fans OPERABLE, restore the inoperaole spray l system to OPERABLE status within 7 days or ce in at least HOT STANDBY within the next 6 hours.and in COLD SHUTDOWN within the following 30 hours,
- b. With two containment spray systems inoperable and at least (four)
O containment cooling fans OPERABLE, restore at least one spray system to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUT 00WN within the following 30 hours. Restore both spray systems to OPERABLE status within 7 days of initial loss or be in at least HOT STANDBY within the next 6 hours and in COLD SHUT 00WN within the following 30 houes.
- c. With one containment spray system inoperable and one group of required containment cooling fans inoperable, restore either the inoperable spray system or the inoperable group of cooling fans to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUT 00WN within the following 30 hours.
Restore both the inoperable spray system and the inoperable group of cooling fans to OPERABLE status within 7 days of initial loss or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. SURVEILLANCE REQUIR04ENTS 4.6.2.1 Each containment spray system shall be demonstrated OPERABLE:
- a. At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed or otherwise secured in position, is in its correct position.
O W-ICE CONDENSER 3/4 6-178 MAR 15 E78
CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- b. By verifying, that on recirculation flow, each pump develops a discharge pressure of greater than or equal to / Sa~psig when tested pursuant to Specification 4.0.5.
- c. At least once per 18 months, during shutdown, by:
- 1. Verifying that each automatic valve in the flow path actuates to its correct position on a -
. test signal., r_h x we.m.,',.a.nt -
, ,,,,g,
( ,
+ c. f S *
- d. At least once per 5 years by performing an air or smoke flow test through each spray bc-ader and verifying each spray nozzle is unobstructed.
9 O W-ICE CONDENSER 3/4 6-188 MAR 15 E8
l
/' /) n *
(
, ,CINTAINMENhSYSTEMS o
3/4.6.2 OEPRESSURIZATIONANDCOOLING.SYSTlMS CONTAINMENT SPRAY SYSTEM / '
- v. l /
( LIMITING CONDITION FOR OPERATION' 0 fa 6.2 eyden j Nt ain , , m - OPER,A81.Jwo ch spfay *-sin,ca,.the[ cont .. en '
- an t
, , pab'l ray syste suc
- 41 be/
\ /yr ection * ,c.e cent .ept' [ser ,/
, ' o ,thk R % and
_ /' -
/
,6 ' ,-
PPGCK8ILIT_V tS ', and 4. 4// / ,., ACTION ,: / - ' WiJt d tairune T r train n erable st
*rai tJV0PERA81.E ta t' withJ le i e spray re cre ours of i t le,a TNpYyidin
,t'hVnext ,48the ours,rprxte 6 Jtours; in,ths db inoperaMe, spray, grain to OPESABLE statuVwithin CgtD SHUT 00WN within the foi t' wing 3Vha6rs. ,-
/
, SURY_ LLANCE-
- _ IREMENTS / '!
- c. /c' crf t spra a:fiiin 's
/ monstrate
,. a
,/ ,/ /
' BLE:
t
/ .. fon ,.ted p'oer' 31 ays by pr/ i fyi that ea v autom ) fin '(m ,
or 't ,. f),cw'p t <i,s no ked, se. - 'd -p'os'
.10 ,.
iosr' i sf ' ' t's correc
/
/ /
p{ By v 'n th on di ir al rge ,pye,s re 'gr fl e h pump (dvelo a, er than o /equ,a to 185 suan[,(o ca np . . g en tc'5st d st er i ~ months da g's3down, - ," ri g at e oma 'c v its ei he f a ctuates rr p ion ontal en fr1Se r'/ test ase 8 da b' 2. greWe d 5 Verifying that each spray pump is prevented from starting by c_., , the Containment Pressure Control System when the containment N atmosphere pressure is less than or equal to 0.25 psid. , 3. Verifying that each spray pump discharge valve is prevented from opening by the Containment Pressure Control System when > 0.25containment the psid. atmosphere pressure is less than or equal to ,/
~
, V McGUIRE - UNIT 1 tio,; t 2- 3/4 6 '.8B (L AM
f:' l' 'c d f f ~2 - r cl _
\
CkAINMENTSYSTEMS / SPRAY ITIVE SYSTEM (OPTMNAL) / LIMITING COND TION FOR OPERATION / 3.6.2.2
\
The spray dditive system snall be OPERABLE with: / l /
- a. A' spray add 1 ive tank containing a volume of between and gallon of between and perc t by weight NaOH solution, and p
- b. Two spray additi eductors each capable of adding NaOH solution from the chemical \dditive tank to a contaffmant spray system pump l
flow. / APPLICABILITY: MODES 1, 2, 3 and 4. , ACTION: /
/
With the spray additive system inope able,frestore the system to OPERABLE status within 72 hours or be in at lekqt Jf0T STANDBY within the next 6 hours; restore the spray additive system to O BLE status within the next 48 hours or be in COLD SHUTDOWN within the foil g 30 hours. O SURVEILLANCE REQUIREMENTS 4.6.2.2 The spray additive sy tem shall be demons rated OPERABLE:
- a. At least once per 1 days by verifying tha. each valve (manual, l power operated o automatic) in the flow pat that is not locked, sealed, or othe ise secured in position, is its correct position.
- b. At least once er 6 months by:
l 1. Verify g the contained solution volume in t tank, and
- 2. Veri ing the concentration of the NaOH soluti by chemical ana ysis.
- c. At le t once per 18 months during shutdown, by verifying that each i autoplatic valve in the flow path actuates to its correct osition on j a / test signal.
- d. At'least once per 5 years by verifying each solution flow rate (to e determined during preoperational tests) from the followin drain connections in the spray additive system:
l
- 1. (Drain line location) gpm
- 2. (Drain line location) gpm W-ICE CONDENSER
,/
3/4'li-IIr MAR 151978
~S 'Ft-' .e - -ege r .. , _, , , , . , , , , ,
- ~
. . . - . - . - . . - . . . ~ . - - - - -
v
. /de
\ CONTAINMENT SYSTEMS
\ /,
CONTAINMENT COOLING SYSTEM (OPTIONAL) (Credit taken for iodine re val by spr systems) LIMITI CONDITION FOR OPERATION
\ ,/
3.6.2.3 (Two) independent groups of containment cooling / fans shall be OPERA 8LE with (two) fan systems to each group. (Equivalent to 0% cooling capacity.) APPLICA8ILITY: MODES 1, 2, 3 and 4. ACTION:
- a. With one group of the absve require containment cooling fans inoperable and both containment spray systems OPERA 8LE, restore the inoperaole gra,y of cooling fans go OPERABLE status within 7 days or be in at least h0T STANOBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
- b. With two groups of e abov equired containment cooling fans incoerable, and both containment spray systems OPERA.8LE, restore at least one group of coollng fans to OPERA 8LE status within 72 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDCWN within the foMowing 30 hours. Restore both above required groups of cooling fans' to GPERABLE status within 7 days of initial -
loss or be in at least HOT STANDBY s within the next 6 hours and in g 30 hours. COLD SHUTD0kN with)n the folic
- c. With one group of the above requized containment cooling fans inoperable and pne containment spray system inoperable, restore the inoperable spray system to OPERA 8LE' status within 72 hours or be in at least HOT TANDBYwithinthenext\hoursancinCOLDSHUTOOWN within the ollowing 30 hours. Restor containme cooling fans to OPERABLEtatus s% the inoperaDie within grouc 7 days of of initial loss or in at least HOT STANDBY within the next 6 hours and in COLD SH OWN within the following 30 hour SURVEILLANCE , OUIREMENTS 4.6.2.3 ch group of containment cooling fans shall be demangtrated OPERA 8LE:
\
- a. At least once per 31 days by:
- 1. Starting each fan group from the control room and v cifying that each fan group operates for at least 15 minutes.
K
- 2. Verifying a cooling water flow rate of greater than or' equal to gpm to each cooler. '
- b. At least once per 18 months by verifying that each fan group starts automatically on a test signal.
W-ICE CONDENSER pK MAR 157979
pc h h e V -t0NTAINMENT SYSTEMS ' /
/
CONTAINMENT COOLING SYSTEM (OPTIONAL) (No credit taken for iodine removal by/ spray systems) /
/
LIMITING CONDITION FOR OPERATION - N 3.6.2.3 (Two) independent groups of containment cooling fans shall be OPERABLE
/
with (two) fan systems to each group. (Equivalent to 100% coolfng capacity.) APPLICABILITY: \ MODES (,2,3and4. ACTION: \
\
- a. With one group of\the above required contai ent cooling fans inoperableandbotNcontainmentspraysystemsOPERABLE,restorethe inoperable group of cooling fans to OPERAgLE status within 7 days or be in at least HOT STa.NDBY within the next 6 hours and in COLD SHUTDOWN within the fo lowing 30 hours
- b. With two groups of the above requir d containment cooling fans inoperable, least one groupand both containment of cooling Yans topOPERABLE status within 72 hoursray systems OPERAB O v or be in at least HOT STAND 8Y w/ thin the next 6 hours and in COLD SHUTDOWNwithinthefollowingh0 hours. Restore both above required groups of cooling fans to OP SLE status within 7 days of initial loss or be in at least HOT TAND Y within the next 6 hours and in COLD SHUTDOWN within the llowin 30 hours.
- c. With one group of the ove require containment cooling fans inoperable and one co tainment spray ystem inoperable, restore either the inoperabl group of containment cooling fans or the inoperable spray s tem to OPERABLE stabus within 72 hours or be in at least HOT STA Y within the next 6 ho\ irs and in COLD SHUTDOWN within the foll ing 30 hours. Restore bo'th the inoperable group of containment co ing fans and the inoperable' spray system to OPERABLE status withi 7 days of initial loss or be in\at least HOT STANOBY within the xt 6 hours and in COLD SHUTDOWN within the following 30 hours.
SURVEILLANCE RE IREMENTS
\
4.6.2.3 Ea group of containment cooling fans shall be demonstrated. OPERABLE:
\
- a. At least once per 31 days by: \
- 1. Starting each fan group from the control room and verifying that each fan group operates for at least 15 minutes.
W-ICE CONDENSER dgA418' MAR 151979
-- - --.. _.._ ____ _ _ ^- --. - ._ .
M AINMENT SYSTEMS SURVE REOUIREMENTS (Continued)
/
/
- 2. Verifying a oli ter ficw rate of greater than or equal to gpm to eac c r.
- b. At least once er 18 months by ve ing that each fan grouc j starts aut atically on a test al.
,/ i 8 O
I O
- l gag 3 5 7gy E' ICE CnNDENSER
(_.3/4 6f2kV
/
st arf'"hv~/ CQ!iTAINMENT SY$TEMS 3/4.6 IODINE CLEANUP SYSTEM (OPTIONAL) N LIMITING CON 0'ITION FOR OPERATION /
/
3.6.3 Twoinde\ pendent containment iodine cleanup systems shall be OPERABLE. APPLICABILITY: MODE 1, 2, 3 and 4. ACTION: With one iodine cleanup syss a inoperable, restore th inoperable system to OPERA 8LE status within 7 days or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN wit 'n the following 3 Vhours. SURVEILLANCE REQUIREMENTS 4.6.3 Each iodine cleanup system shall e demonstrated OPERABLE:
- a. At least once per 31 days o a SiAGGERED TEST BASIS by initiating, from the control room, flow throug the HEPA filters and charcoal l O adsorbers and verifying pfiat the sys hours with the heaters n.
operates for at least 10
- b. At least once per 18 onths or (1) after a structural maintenance on the HEPA filter charcoal adsorber hou ngs, or (2) following painting, fire or emical release in any ven lation zone communi-cating with the s stem by:
- 1. Verifying hat the cleanup system satisfies th in place testing acceptan e criteria and uses the test procedure of Regulatory Positi s C.S.a, C.5.c and C.5.d of Regulatory Gu de 1.52, Revis n 2, March 1978, and the system flow rate is\ cfm !
10%. . 2. VeAfyingwithin31daysafterremovalthatalaboratoryanalysis ( gf a representative carbon sample obtained in accordance w'14h egulatory Position C.6.b of Regulatory Guide 1.52, RevisionN2, March 1978, meets the laboratory testing criteria of Regulato'ry Position C.6.a of Regulatory Guide 1.52, Revision 2, March \ 1978. N
- 3. Verifying a system flow rate of cfm 2 10% during system operation when tested in accordance with ANSI N510-1975.
O W-ICE CONDENSER 3Nd-M MI B79
_. . . _ _ _ _ . _ - .._m . ._ . . . COM AINMENT SYSTEMS SURVEIL CE REOUIREMENTS (Continued) _
,/
- c. After ver/ 720 hours of charcoal adsorber operation by verifying within days after removal that a laboratory analysis of a repre-sentative ,arbon sample obtained in accordance with Regulatory Position C.6 of Regulator / Guide 1.52, Revision 2, March 1978, 1 meets the labc atory testing criteria of Regulatory Position C.5.a of Regulatory GL'de 1.52, Revision 2, March 1978. '
- d. At least once per 1 months by: ,
/
- 1. Verifying that the ' pressure drop across the combined HEPA filters and charcoalNadsorber banks is less than (6) inches Water Gauge while operating the system at a flow rate of cfm 10%.
\
- 2. Verifying that the system starts on either a Safety Injection Test Signal or on a Containme'nt Pressure -High Test Signal.
A
- 3. gb Verifying by operator that the filter action. cooJin' e
\ypass valves can be opened
- 4. Verifying that the heataps dissipate
/ \i kw when tested in accordance with :
ANSI N510-1975.
- e. After each complete or artial replacement of a HEPA filter bank by
, verifying that the HEP filter banks remove greater than or equal to ( (99.95)%" of the 00P en they are tested in place in accordance with ANSI N510-1975 hile operating the system at 'a flow rate of cfm t 10%.
- f. After each cc ete or partial replacement of a charcoal adsorber bank by veri ing that the charcoal adsorbers remove gr'e ater than or equal to 9 .95% of a halogenated hydrocarcon refrigerant \ test gas when the are tested in place in accordance with ANSI N510-1975 while erating the system at a flow rate of cfm \10%.
\\
\
\
, \
99.95% pplicable when a filter efficie,cy of 99% is assumed in the safety anal es; 99% when a filter efficiency of 90% is assumed. \ 1 1 O W-ICE CONDENSER /3/4 [-J48' APR 151978
l CONTAINMENT SYSTEMS 3/4.6.4 CONTAINMENT ISOLATION VALVES l LIMITING CONDITION FOR OPERATION l
^
3.6.p The containment isolation valves specified in Table 3.6-2 shall be OPERABLE with isolation times as shown in Table 3.6-2. APPLICABILITY: MODES 1, P., 3 and 4. ACTION: With one or more of the isolation valve (s) specified in Table 3.6-2 inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and either: o
- a. Restore the inoperable valve (s) to OPERABLE status within 4 hours, or
- b. Isolate each affected penetration within 4 hours by use of at least one deactivated automatic valve secured in the isolation position, or
- c. Isolate each affected penetration within 4 hours by u::e of at least one closed manus 1 valve or blind flange, or d Be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
SURVEILLANCE REQUIREMENTS 3 4.6.W.1 The isolation valves specified in ' Table 3.6-2 shall be demonstrated OPERA 8LE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by performance of a cycling test and verification of isolation time. l l O W-ICE CONDENSER 3/4 6-jet M1 M MF
- - , , _ . _ ,,,w ,,,m,.sm -w.m='-w--v vm-->=M 'a 9 -
CONTAINMENT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) 3 4.6.#'.2 Each isolation valve specified in Table '.6-2 shall be demonstrated OPERABLE during th: COLD SMUT 00'J' :r 'EFUELL"G "00E- at least once per 18 months by:
- a. Verifying that on a Phase A containment isolation test signal, each Phase A isolation valve actuates to its isolation position.
- b. Verifying that on a Phase B containment isolation test signal, each Phase B isolation valve actuates to its isolation position.
unili 514;i n*cn (p )
- c. Verifying that on a Luwo h....mnt 'urg; :nd Exh;ust isolation test signal, each Purge and Exhaust valve actuates to its isolation position.
1 4.6.#.3 The isolation time of each power ocerated or automatic valve of Table 3.6-2 shall be cetermined to be within its limit when tested pursuant to Speci fication 4.0. 5._ _ _ N N I [ .- o Scx /hce,-? /! e < " j ~ R f G . -
'N O
'f-ICE CONDENSER 3/4 6-7AS 2c 5 SEP 2 81981
l CONTAINMENT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued)
-l
- 4. 6. 3.1 Each Containment Purge isolation valve shall be demonstrated OPERABLE within 24 hours after each closing of the valve, except when the valve is being used for multiple cyclings, then at least once per 72 hours, by verifying that wnen the measured leakage rate of these valves is added to the leakage rates determined pursuant to Specification 4.6.1.2.c for all other Type 8 and C penetrations, the comoined leakage rate is less than or equal to 0.60 L .
3 77, 3 e r- f f0 f'. Y b ~2' S
? \
l i l' J D S e ,~pf-McGUIRE - UNIT 1 M 2P l l
b
/ ; O V I
1ltllt E 3. 6 -2 i s !' O. i c CONTAINMfNI ISul AIION val VI'. k ll VALVE NUMllER HAXIMUM ISOLATION p, l } +snc filNCI' ION TIME ISEC.) l : t 1 ! 1N] A. PilASE "A" ISOLA'll0N -l ! i; p 88-18# Steam Generator lA Blowdown Containment Outside Isolation 110 BB-28# . i ' BB-38# Steam Generator IB lilowdown Containment outside isolation <10 1 08-48# Steam Generator IC Blowdown Contain.wnt (nel side Isolation 310 l' Bil-SA# Steam Generator 10 blowdown Containment Outside Isolation 110 l Steasii Gelierator lA B1owdown Containmu.t inside Isolation l BB-6A# 110 g BB-7A# Steam Generator 1B Blowdown Containment loside Isolation 110 , f) BB-8A# Steam Generator IC Blowdown Containment inside Isoletion <10 BB-140A Steam Generator ID Blowdown Containment inside Isolation 210 BB-141A Steam Generator IA Blowdown Containment Inside isolation 701 - M BB-142A Steam Generator IB Blowdown Containment inside Isolation 210 .'\ , BB-143A Steam Generator IC Blowdown Containment Inside Isolation 210 [ Steam Generator 10 Blowdown Containment inside Isolation 310 j\\.
- CF-26AB#
CF-28AB# Steam Generator 10 feedwater Containment isolation (S k CF-30AB# Steam Generator IC feedwater Containisient Isolation IS Steam Generator IB feedwater Containment isolation ,h g CF-35AB# Steam Generator IA feedwater Containment Isolation 75 75 ' CF-1268 Steam Gesierator IA Hain feedwater to Auxiliary feedwater i ' ! Nozzle Isolation 510 CF-1270 ! 4) / Steam Generator 10 Hain feedwater to Auxiliary f eedwater ~<10 / Nozzle Isolation i
}
CF-1280 Steam Generator IC Main feedwater to Anxiliary feedwater
/
Nozzle Isolation -<10 Cf-1298 Steam Generator 10 Hain feedwater to Auxiliary feedwater Nozzle Isolation -<10 CF-134A CF-135A Steam Generator lA f eedwater Containment Isolation Bypass $10 CF-136A Steam Generator 18 f eedwater Containment isolation Gypass 110 CF-137A Steam Generator IC feedwater Contaisirtient. Isolatio:. bypass 110 CF-ISlA Steam Generator ID feedwater Containment isolation Bypass 110 Auxiliary Nozzle lemper SGIA 110 e G 9
)
l I Allll 3.6-2 (Continued) 1
@ CONIAINilfNI ISOLATION VALVf5 '
, E m
' NAXIMUM ISOLATION RE VALVE NUMBER FUNCTION N 8 A. PilASE "A" I50LATION TIME (SEC.)
'i p CF-153A Auxiliary Nozzle Tesnper SGIB $10 CF-1558 Auxiliary Nozzle Temper SGIC CF-IS78 510 Auxiliary Nozzle Temper SGID $10 KC-305B# Excess Letdown lix Supply Pent. Isolation (outside)
KC-315B# 130 KC-320A Excess Letdown lix Ret. Ildr. Pent. Isolation (outside) 530 NCDI lix Supply lidr. Pent. Isolation (outside) $15 KC-3328 NCDT lix Supply lidr. Pent. Isolation (inside) w KC-333A $15 2 KC-429B NCDI ilx Return lidr. Pent. Isolation (outside) <l5 cn KC-430A RB Drain lleader Inside Containment Isolation IIS RB Drain lleader Outside Containment Isolat ion 515 h w' AM NB-2608 Reactor Hakeup Water Iank to NV System
% 115 NC-538 Nitrogen to Pressurizer Relief lant #1 Containaient $10 Isolation Outside NC-54A Hitrogen to Pressurizer Relief Tant #1 Contairunent Isolation Inside $10 NC-568 PRI #1 Hakeup <10 NC-1958 NC Pump Hotor Oil Containment Isolation Gutside NC-196A 715 NC Pump Hotor Oil Containment Isolation inside 315 i
NF-228A Unit 1 Air flandling Units Glycol Supply Containment -<15 luolation Dutside NF-233A Unit I Air flandling Units Glycol Supply Containment -<15 Isolation loside NF-234A Unit i Air flandling I; nits Glycol Supply Containn.ent Isolation Outside -<l5 NI-47A Accumulator 11 Supply Outside Containment Isolation NI-95A lest ilDR Insille Omtainment Isolation
< lt /. I 310
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9 9 i a 2 1ADil 3.di-2 (Continued) E
- S CastIAlt)tilil ISDI AIlON VAIViS E
I HAXIHlM i gc ISOLAIION g VAtWE IBSaf t fis0Cil0N llME (SEC.)
~
A. PHASE "A" 1506AI1018 F 80t-221Af SG 10 Sample ikfr. Containment Isolation Outside <l5 W-Jus letdonai Containment Isolation Dutsida W-94Af $10 lic Passps Seal Return Containment Isolaion inside $10 W-9588 NC Pamps Seal Return Containment Isolat ion outside W-24585 $10 Claarying Line Containeent IsolaLion Dutsitie <10 W-457Af 45 ggn:a tetdown Orifice Outlet - Contairm ut Isolation <l5 W-458A# 75 gpa letdown Oritice Outlet - Contalw ent Isolation W-459Af $15 i liigh Pressurizer Letdown Grifice Outlet - Contaissent $15 A Isolation 1 / W-849A Stan6uy Hakeup Puqi to RCS seals
$15 8
m l
/ RF-821 A Contaisuent Isolation Outside linit 1 $15
/ SM-SAB h in Steaa 3D isolation Bypass Ctrl. <S j SM-10A8 SM-11A8 m in Steam IC isolation Bypass Ctrl. $5 min Steam 18 Isolation Bypass Ctri. <S
[ SM-12A8 m in Steam lA Isolation Bypass Ctri. ES f VB-496 Breathing Air Unit I Containment isolation <l5 - VE-SA Containment #2 Purge to Annulus insid. Containa:ent isolation <1S VL-68 Containment #2 Purge to Annulus Outside Contain:sent Isolation ( VE-10A 215 i Containment #2 Purge Blower Outlet, Containment Isolation 215 (outside) ~
\ VI-1488 Instras. Air Upper Containment Outsiife Isolation < l5 y ._
~ gy-Uf 2 A C SfamNy % l. ~ Sw /-
hc4 /n n,e Zn/%, L; /<
, ~
. 2 ~~~al -' B^
i 8 ov O O c TABLE 3.6-2 (Continued) h l CONTAINHENI ISOLATION VALVES
< ~
d5
. HAXIHUH ISOLA 110N Rs VALVE NUMBER FUNCTION TIME (SEC.)
9 h A. PHASE "A" ISOLATION b VI-362A RB isolation Valve for VI Sup;>ly to Annulum Vent. 515 VP-1B** Upper Contairunent Purge Supply #1 Outside Isolation VP-2A** $3 Upper Containment Purge Supply #1 Inside Isolation $3 VP-3B** Upper Containment Purge Supply #2 Outside Isolation VP-4Aa* $3 Upper Containment Purge Supply #2 Inside Isolation 13 VP-6B^^ Lower Containment Pur0e Sur,,1y #1 Outside isolation VP-7A** $3 Lower Containment Purge Supply #1 Inside Isolation 13 VP-88** Lower Containment Purge Supply #2 Outside Isolation VP-9A^^ 13
, Lower Containment Purge Supply #2 Inside Isolation 13 g VP-10A** Upper Contaiament Purge Exhaust #1 Inside Isolation VP-11B** 13
, Upper Containment Purge Exhaust #1 Outside Isolation 13 e VP-12A** Upper Containment Purae Exhaust #2 Inside Isolation 53 2ii VP-138** Upper Containment Purge Exhaust #2 Outside Isolation VP-ISA** 13 h lower Containment Purge Exhaust #1 Inside Isolation 13
# VP-16B** Lower Containment Purge Exhaust #1 Outside Isolation I VP-17Aa*
<3 Incore Instru. Room Purge Supply Inside Isolation 33 VP-188** Incore Instru. Room Purge Supply Outside Isolation VP-19A** 13 Incore Instru. Room Purge Exhaust inside Isolation 13 VP-20B** Incore Instru. Room Purge Exhaust Outside Isolation $3 VQ-IA Containment Air Helease Inside isolatiun VQ-28 53 Containment Air Helease Outside Isolation 13 VQ-50 Containment Air Addition Outside Isolation VQ-6A $3 Containment Air Addition Inside Isolation 53 VS-128 Unit 1 Containment Station Air Outside Isolation $15 VX-31A Containment Atmosphere Inside Isolation VX-338 Containment Atmosphere Inside Isolation $5
$5 e O G
I p 7-w N) N) TABLE 3.6-2 (Continued} CONTAINMEN1 ISOLA 110N VALVES o
- HAXIMUM
' ISOLA 110N E VALVE NUMBER ItlNCIION llME (SLC.) --- A PHASE "A" ISOLAT10N F NCDT Pumps Discharge Outside Containment Isolation $10 WL-18 WL-2A NCDT Pumps Discharge Inside Containment Isolation $10 NCDI Vent inside Containment Isolation <10 WL-39A NCDT Vent Outside Containment Isolation 210 WL-41B WL-64A RB Sump Pump Discharge Inside Containment Isolation 315 WL-6SB RB Sump Pump Discharge Outside Containment Isolation $15 Containment Vent Unit Urains Inside Containment Isolation <15 WL-321A WL-3228 Containment Vent Unit Drains Outside Containment Isolation 515 YM-115C Demin. Water Containment Outside Isolation $15 w
1 B. PHASE "B" ISOLATION cn g KC-338B NC Pump Supply lleader Pent. Isolation (outside) $40 KC-4248 NC Pumps Return lidr. Pent Inside Isolation $40 KC-425A NC Pumps Return lidr. Outside Isolation 140 i RN-2528 Nonesse.itial Supply to RB Penetration Outside Isolation $30 RN-253A Nonessential Supply to RB Penetration Inside Isolation $30 Nonessential Return to RB Penetration Outside Isolation <30 RN-276A RN-27/8 Nonessential Return to RB Penetration Inside Isolation {30 RV-32A Lower Containment Vent. Unit Supply Containment Isolation 160 (outside) RV-338 Lower Containment Vent. Unit Supply Containment Isolation 160 (inside) RV-76A Lower Containment Vent. Unit Discharge Containment Isolation $60 (inside) RV-778 Lower Containment Vent. Unit Discharge Containment Isolation 160 (outside) VI-1298 "A" lleader Containment Outside Isolation <15 VI-1508 Instrument Air Lower Containment Outside Isolation 215 VI-1608 "B" lleader Containment Outside Isolation 315 1
,$i
( (" n L (U) r TABLE 3.6-2 (Continued) 5 CONTAINMEN1 ISul Afl0N VALVIS MAXIMUM tc 150LAlION D* VALVE NUMBER IUNCIION TIME (SEC.) N --i B. PilASE "B" ISOLATION g) Upper Containment Vent. Unit Supply Contaisunent Isolation (outside) 530 RV-79-A i RV-808 Upper Containment Vent. Unit Supply Containment isolation (inside) 530 ' RV-101A Upper Containment Vent. Unit Discharge Containnuent Isolation (inside) 530 RV-1028 Upper Containment Vent. Unit Discharge Containment Isulation (inside) 530 SM-LAB # Hain Steam ID Isolation <5 '..' SM-3AB# Hain Steam IC Isolation 75 SM-SAB# Main Steam 18 Isolation 75 SM-7AB# Hain Steam 1A Isolation 75 l w SM-9AB# Main Steam 10 Isolation Bypass Ctrl. 75 , b 1 SM-10AB# Main Steam IC Isolation Bypass Ctri. 75 i cn SM-11AB# Main Steam 18 Isolation Bypass Ctrl. 75 l i g SH-12AB# Main Steam 1A isolation Bypass Ctri. 15
/
14 C. MANUAL NC Pump Motor Oil Drain N/A l
- 1. INCL 41* ,
N/A ,'
- 2. INCL 42* NC Pump Motor Oil Drain
- 3. 1WE13* Equipment Decontamination N/A ,
- 4. 1WE23* Equipment Decontamination N/A l i
- 5. IVXJ4* Containment il Sample N/A 1
- 6. IVX40* Containment il Sample N/A I
- 7. IFW11* Refueling Wat r N/A l i
- 8. IfWl3* Refueling Water N/A
- 9. IfW4* Refueling Water N/A -
N ' E
* *May be opened on an intermittent basis under administrative control.
^^ Valve also receives a liigh Radiation (11) isolation signal.
$ #Not subject tn Type C leakage tests.
~
NOTE: Times are for valve operation only, and do not include any sensor response or circuit delay times. See 3/4 3.2 for system actuation response times. S 0 e ,
O O x o' I Alli t 3.6-2
+
h CONIAlHMINI 150LAll0N VAlVIS m a
; o .i E MAXIMUM i' y VALVE NHH0ER IUNCTION ISOLATION IINE (Seconds) m !. A. PilASE "A" ISOLATION
- 1. ,
2. B. PilASE "B" ISOLATION
- 1. !
2. C. CONTAINMENT PURGE AND EXilAUSI
%, 1. t w,
D 2. U w, D. N UAL P.
- 2. ( h.
t E. 0 tiler w
- 1. N 2.
M May be opened on an intermittent basis under administrative control. N **The provisions of Specification 3.0.4 are not applicable. i l"j Not subject to Type C leakage tests.
CONTAINMENT SYSTEMS 3/A.6.5 COMBUSTIBLE GAS CONTROL HYDROGEN MONITORS LIMITING CCNDITION FOR OPCRATION V 3 6.5.1 Two independent containment hydrogen monitors shall be OPERABLE. APPLICABILITY: MODES 1 and 2. ACTION: l l With one hydrogen monitor inoperable, restore the inoperable monitor to OPERABLE status within 30 days or be in at least HOT STAND 8Y within the next 6 hours. SURVEILLANCE REQUIREMENTS 4.6.F.1 Each hydrogen monitor shall be demonstrated OPERABLE by the performance O of a CHANNEL CHECK at least once per 12 hours, a ANALOG CHANNEL OPERATIONAL TEST at least once per 31 days, and at least once per 92 days on a STAGGERED TEST BASIS Ays,qen yes by m p:xtwaserforming M e 6 hais, CHANNEL c a /;4 CALIBRATION m h*c > pelats using
'e, f <:::le
- 3aa c= t:fa %c-
~-
- a. 4ne volume percent hydrogen A lanue n : tre; h re
- b. Geer volume percent hydrogen A louc n:tr:gca_.
l
$ne l
l W-ICC. CONDENSER 3/4 6-288 3EP 151981
O CONTAINMENT SYSTEMS ELECTRIC HYOROGEN RECOMBINERS - W LIMITING CONDITION FOR OPERATION y 3.6.J.2 Two independent containment hydrogen recombiner systems shall be OPERABLE. APPLICABILITY: MODES 1 and 2. ACTION: With one hydrogen recombiner system inoperable, restore the inoperable system te OPERABLE status within 30 days or be in at least HCT STANDBY within the next 6 hours. , SURVEILLANCE REQUIREMENTS 4 4.6.5.2 Each hydrogen recombiner system shall be demonstrated OPERABLE: l
- a. At least once per 6 months by verifying during a recombiner system functional test that the minimum heater sheath temperature increases to greater than or equal to 700*F within 90 minutes. Upon reaching 700*F, increase the power setting to maximum power for 2 minutes and verify that the power meter reads greater than or equal to 60 Kw.
- b. At least once per 18 months by:
- 1. Performing a CHANNEL CALIBRATION of all recombiner instrumentation and control circuits,
- 2. Verifying through a visual examination that there is no evidence of abnormal conditions within the recombiners enclosure (i.e. , loose wiring or structural connections, deposits of foreign materials, etc.), and
- 3. Verifying the integrity of all heater electrical circuits by performing a resistance to ground test following the above required functional test. The resistance to ground for any heater phase shall be greater than or equal to 10,000 ohms.
O P ICE CONDENSER 3/4 6-298 AUG 6 1981
-w,- +--.-w -y--v- w-- , y . , ,--.+ q. wrw----c-- r ----**-w T--- -w * ----- + - - - - -----++-u '
pc---
1 l fIf GQh' ONTAINMENT SYSTEMS HY ROGEN PURGE CLEANUP SYSTEM (If less than two hydrogen recemoiners available) x LIMITINdxCONDITION FOR OPERATION / f 3.6.5.3 A containment hydrogen purge cleanup system . 11 be OPERABLE and capable of beingNpowered from a minimum of one OPERABLE emergency bus. APPLICABILITY: MCC 5 1 and 2. ACTION: /
/
With the containment hydrogen purge cleanup system (noperable, restore the hydrogen purge cleanup systhm to OPERABLE status dthin 30 days or be in at least HOT STANOBY within 6 hours. N\ / SURVEILLANCE RECUIREMENTS /
\ /
\
4.6.5.3 The hydrogen purge cleanup s em shall be demonstrated OPERABLE: a. At leastthe through once HEPAper 31 and filters daycha'rcoal [s b'y i itiating, adsortersfrom the control and verifying that recm, ficw the system operates for'at least 10 hours with the heaters on. p \
- b. As least once per 1 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorb'er housings, or (2) following painting fire or hemical release in ah ventilation ::ene communicating w h the system by:
- 1. Verifyi that the cleanup system sat sfies the in-place testin acceptance criteria and uses ofstest procedures of Regul tory Positions C.S.a, C.S.c and C.j.d of Regulatory Gui 1.52, Revision 2, March 1978, and tte system flow rate is efm 10%. \
( E. erifying within 31 days after removal that laboratory I analysis of a representative carbon sample obtained in ! accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the aboratory testing criteria of Regulatory Position C.6.a o Regulatory Guide 1.52, Revision 2, March 1978.
- 3. Verifying a system flow rate of cfm 10% dur ng system operation when tested in accorcance with ANSI N510-to75.
W-ICE CONDENSER d66-JOB 1
. . = - -- -
ge f .yf/,cs M O CONTAINMENT SYSTEMS SURVEILLANCE RE0VIREMENTS (Continued)
/
- c. Afte'es every 720 hours of charcoal adsorber operation by verifying within\31 days after removal that a laboratory analysis of. a repre-sentati h carbon sample obtained in accordance with Regulatory Position .6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the boratory testing criteria of RegulatoryfPosition C.6.a l of RegulatorysGuide 1.52, Revision 2, March 1978./
d.
\
At least once peg 18 months by: / 1.
\ /
Verifying that'the pressure drop acposs the combined HEPA fi!ters and charcoal acsorber banks is less than (6) inches Water Gauge while'coerating thefsystem at a flow rate of cfm t 10%.
\ ,/
- 2. Verifying that tne fil'ter cooling ::ypass valves can be manually openec.
\\
- 3. Verifying that the he ers' dissipate t kw when tested in accordance/with ANSI N510-1975.
\ e. After each complete or~ partial replacement of a HEPA filter bank by verifying that the HEPA filter banks r.emove greater than or equal to (99.95)%" of the DOP when they are tested in place in accordance with ANSI N510-1975 while operating the ' system at a flow rate of cfm TO%.
N
\
- f. After each c plete or partial replacement of a charcoal adsorber bank by ver .ying tha.t the charcoal adsorbers\ remove greater than or equal to .95% of a halogenated hydrocarbon refrigerant test gas when the aretestedinplaceinaccordancewithyNSIN510-1975 while erating the system at a flow rate of s cfm 10%.
N l
\
N l R / N 99./35% applicable when a filter efficiency of 99% is assumed in the safety analyses; 99% when a filter efficiency of 90% is assumed.
/
O W-ICE CONDENSER N 4L6 4 APR 151978 l I
f. 4 , 5 f M' I[G ' l' O CONTAINMENT SYSTEMS ( HYOROGEN NIXING SYSTEM (OPTIONAL) N, ' LIMITING CONDITION FOR OPERATION /
- 3. 6.4 'Two 5.Nindependent hydrogen mixing systems'shall be OPERABLE.
N / APPLICA8ILI MODES 1 and 2. ACTION: With one hydrogen mixing system inoperable, restore the inoperable system to OPERABLE status within 30 days or be in at least HOT STANDBY within the next
~
6 hours. s / N ./
'v'
/\
'N SURVEILLANCE REOUIREMENTS' \
'\
4.6.5.4 Each hydrogen mixing system shall be\ emonstrated d OPERABLE:
- a. At least once per 92 days on a STAGGEREDs. TEST BASIS by starting each system from the control room and verifyingsthat the system op.erates for a least 15 minutes. N
- b. Adleast once per 18 months by verifying a system flow rate of at N
least cfa. ,
/
/ \s
/
O P ICE CONDENSER ($/41[-32ff AUG 6 1981 i
/, -
7'- ctf'C'l' D'!' Os
~
CONTAINMENT SYSTEMS 3/4.6 6< PENETRATION ROOM EXHAUST AIR CLEANUP SYSTEM (OPTIONAL) /
\
LIMITING CONDITION FOR OPERATION
\
3.6.6 Twoindependentcontainmentpenetrationroomexhaustdircleanup systems shall be RABLE. / 7 APPLICABILITY: MODE 1, 2, 3 and 4. j/ ACTION: j With one containment pene tion room exhaust ai 'bleanupsysteminoperable, restore the inoperable sy to OPERABLE statu /within 7 days or be in at least HOT STANDBY within the ext 6 hours and in COLD SHUTOOWN within the following 30 hours. /
/
SURVEILLANCE REQUIREMENTS / o l O 4.6.6 Each containment penetrationf room exhaust air cleanup system shall be demonstrated OPERABLE: l a. At least once per 31,d'ays on a STAGGERED TEST BASIS by initiating, from the control ro9m, flow throu the HEPA filters and charcoal adsorbers and veri ing that the s tem operates for at least 10 hours with the h ters on.
- b. At least once er 18 months or (1) afbr any structural maintenance on the HEPAfilter or charcoal adsorber\h ousings, or (2) following painting, f,fre or chemical release in an ventilation zone communi-cating within the system by:
- 1. Ver fying that with the system operatin at a flow rate of
'fm 10% and exhausting through the HEPA\ filters and charcoal
, adsorbers, the total bypass flow of the syhten to the facility vent, including leakage through the system diverting valves, is less than or equal to 1% when the system is t'e;ted by admitting cold 00P at the system intake. (For systems wt h diverting valves.)
/ 2. Verifying that the cleanup system satisfies the in place testing acceptance criteria and uses the test procedures of Regulatory Positions C.5.a, C.5.c and C.5.d of Regulatory Guide l'.'52, l Revision 2, March 1978, and the system flow rate is N cfm 10%.
O W-ICE CONDENSER $4'o'-3W JUN 1 3 79
" " " ,--n,
,w - - -
-, - ys
l A $ 1 i CONTAINMENT SYSTEMS SURVEILLANCE REOUIREHENTS (Continued) ,
'\ '
\ /
Verifying within 31 days after removal that a laboratory anal-N 3. ysis of a representative carbon sample cotained in accordance
\ with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Reguia-I tory Position C.6.a of Regulatory Guide 1.52s Revision 2, March i
1978. 4 Verifying a system flow rate of cfm : 10% during system operation when tested in accordance with ANSI N510-1975.
/
- c. After e ery 720 hours of charcoal adso,rber operation by verifying within 3Ndays after removal that a Yaboratory analy=is of a repre-sentative carbon sample obtained 1 /accordance with degulatory Position C.6'.'b of Regulatory Guide' l.52, Revision 2, March 1978, meets the labovatory testing cr.iteria of Regulatory Position C.S.a of Regulatory G de 1.52, Rev'sion 2, March 1978.
- d. At least once per mont by:
- 1. Verifying that the pressure drop across the combined HE?A filters anc char; O adsorber banks is less than (6) inches
'ar.ter Gauge wh'le op rating the system at a flow rate of efm : 10%.
l 2. 'a ri fyi ng at the syste starts on a Safety Infection Test Signal.
- 3. Verify ng that the filter coo ing b;jpass valves can be manually open .
- 4. Ve ifying that the heaters dissip e t kw when sted in accor6ance with ANSI N51 1975.
- e. After each complete or partial replacement .of a HEPA filter bank by ve/ifying that the HEPA filter banks remove reater than or equal to 9.95)f." of the DOP when they are tested in lace in accordance ith ANSI N510-1975 while operating the syste at a flow rate of cfm t 10%.
. After each complete or partial replacement of a c. rcoal adsorber bank by verifying that the charcoal adsorbers remode greater than or l equal to 99.95% of a halogenated hydrocarbon refrigehant test gas l when they are tested in place in accordance with ANSI 3510-1975 l while operating the system at a flow rate of cfm A 10%.
l l A 99.95% applicable when a 1'lter efficiency of 99% is assumed in the safety ( analyses; 99% when a filter efficiency of 90% is assumed. t t l W-ICE CONDENSER f/(6-3kB- APR 15 ;g7g
_.._.-^. _ __ _ . . _ _ __ _ _ _
)
ib'd f 0ff , CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) N 3. Verifyingwithin31daysafterremovalthatalabar/ atory analysis of a representative carbon sample obtained in accordance with s Regulatory Position C.6.b of Regulatory Guide /1.52, Revision 2,
\ March 1978, meets the laboratory testing cpfteria of Regulatory
\ Position C.6.a of Regulatory Guide 1.52,f evision R 2, March
\l978.
- 4. Verifying a system flow rate of ecfm i 10% during system op'eration when tested in accordance with ANSI N510-1975.
c.
\
After every 720 hours of charcoal adsorber operation by verifying
/ ,
within 31 days after removal that/a laboratory analysis of a repre-sentative carbon sample obtained'in accordance with Regulatory
?osition C.6.'b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52,' Revision 2, March 1978.
\ /
- d. Atleastonceper\l8monthsby:
- 1. Verifying that\ple pressure drop across the combined HEPA q
y, filters and charcoal adsorber banks is less than (6) inches Water Gauge i lgoperating the system at a flow rate of cfm t 10%.
- 2. Verifyin that the s stem starts on a Safety Injection Test Signal.
- 3. Verif ing that the filt r cooling bypass valves can be manually ope d.
4 V rifying that the heaters dissipate t kw when ested in accordance with A I N510-l W
- e. A ter each complete or partial rep cement of a HEPA filter bank cy erifying that the HEPA filter bank remove greater than or equal to (99.95)%" of the 00P when they are t 9ted in place in accordance with ANSI N510-1975 while operating the system at a flow rate of cfm t '0%.
- f. After each complete or partial replacemey of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99.95% of a halogenated hydrocarbon refrigerant test gas when they are tested in place in accordance hith ANSI N510-1975 while operating the system at a flow rate of \ cfm t 10%.
'\
99.95% applicable when a filter efficiency of 99% is assumed in the safety analyses; 99% when a filter efficiency of 90% is assumed. O d/f6-38A, APR 151978 , W-ATMOSPHERIC l
.=aw w. ..-e. .
_%-__ ,._%_ . , _ _ , _ _ r__ _. __ __ _ _ _ , _ _ , - _ _w,
1 I y aff!"'li I CONTAINMENT SYSTEMS 3 4 6.7 VACUUM RELIE: VALVES (OPTIONAL) LIMITINGsCONDITION FOR OPERATION /- l \ - N 3.6.7 The crimary containment to atmosphere vacuum relie OPERABLEwithanactuationsetpointoflessthanorequs[fvdivesshallbe to _ psid. APPLICABILITY: MODE 1, 2, 3 and 4. ACTION: / Withoneprimarycontainm\ / entsto atmosphere vacuum relief valve inoperable, restore 'he valve to OPERABLEsstatus with*in~ 4 hours or be in at least HOT STANDBY within the next 6 hourssand in COLD ' SHUTDOWN within the following 30 hours. \ x ,/
\'
/\
/ 'N N\
O SURVEILLANCE REOUIREMENTS 4.6.7 No ad tional Surveillance Requirements other than those required by Specificat n 4.0.5. s
/
l O l W-ATMOSPHERIC [/4h36A' , JUN I 1379
p*
?
Q,) HYDROGEN CONTROL DISTRIBUTED IGNITION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.4.3 The primary containment distributed ignition system shall be operable. APPLICABILITY: MODES 1 and 2. ACTION: With the distributed ignition system inoperable, restore the inoperable system to OPERABLE status within 7 dava or be in at least HOT STANDBY within the next 6 hours. SURVEILLANCE REOUIREMENTS 4.6.4.3 The distributed ignition system shall be demonstrated OPERABLE: i m a. At least once per 92 days by energizing the supply breakers and l verifying that for every paired circuit at least one circuit has a current reading within the acceptance criteria established during preoperational testing. 1
- b. At least once per 18 months by:
- 1. Verifying the cleanliness of each glow plug by a visual inspection.
- 2. Energizing each glow plug and verifying a surface temperature of at least 1500*F.
l l t t 1 (D
'w)
XB i McGUIRE - UNIT 1 3/4 6-)G( JUN SI l (/V77 2.- l
. . . . . a- r. :. . - . . = .
2-CONTAINMENT SYSTEMS 3/4.6.7 ICE CONDENSER ICE BED LIMITING CCNDITION FOR OPERATION f 3.6.7.1 The ice bed shall be OPERABLE with:
- a. The stored ice having a boron concentration of at least 1800 ppm boron as sodium tetraborate and a pH of,9.0 to 9.5,
- b. Flow channels througn the ice condenser,
- c. A maximum ice bed temperature of less than or equal to 27*F, 3D
- d. A total ice weight of at least (2,721,z.2/C.CO pounds at a 95% level of confidence, and
- e. 1944 ice baskets.
l APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: With the ice bed inoperable, restore the ice bed to OPERABLE status within 48 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUT-DOWN within the following 30 hours. SURVEILLANCE REQUIREMENTS
.5' 4.6.#.1 The ice condenser shall be determined OPERABLE:
- a. At least once per 12 hours by using the ice bed temperature monitor-ing system to verify that the maximum ice bed temperature is less than or equal to 27'F.
- b. At least once per 9 months by:
- 1. Chemical analyses which verify that at least 9 representative samples of stored ice have a baron concentration of at least 1800 ppm as sodium tetraborate and a pH of 9.0 to 9.5 at 20'C.
- 2. Weighing a representative sample of at least 144 e baskets l and verifying that each basket contains at least lbs of A2 /#
ice. The representative sample shall include 6 ba ts from each of the 24 ice condenser bays and shall be constituted of W-ICE CONDENSER 3/4 6-36e JUN 1 1979 \ 3/ B
,. ,n. .- ,v. - __r,. - _ . - - _ , . , , _ ,
CONTAINMENT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) one basket each from Radial Rows 1, 2, 4, 6, 8 and 9 (or from the same row of an adjacent bay if a basket from a designated row cannot be obtained for weighing) wjthin each bay. If any basket is found to contain less thanCii4G'plunds of ice, a N Mjc representative sample of 20 additional baskets from the same bay shall be weighed. The minimum average weight of ice from the 20 additi M baskets and the discrepant basket shall not be less thanG440 pounds / basket at a 95% level of confidence.
/4/C The ice condenser shall also subdivided into 3 groups of baskets, as follows: Group 1 - bays 1 through 8, Group 2 -
bays 9 through 16, and Group 3 - bays 17 through 24. The minimum average ice weight of the sample baskets from Radial Rows 1, 2, 4, 6, 8 and 9 in each group shall not be less than
'z/C 4460 pounds / basket at a 95% level of confidence.
The minimum total ice condenser ice weight at a 95% level of confidence shall be calculated using all ice basket weights determined during this weighing program and shall not be less than c^d2 5 9 pounds. 3,353, xc
- 3. Verifying, by a visual inspection of at least two flow passages per ice condenser bay, that the accumulation of frost or ice on flow passages between ice baskets, past lattice frames, through the intermediate and top deck floor grating, or past the lower inlet plenum support structures and turning vanes is restricted to a thickness of less than or equal to 0.38 inches. If one flow passage per bay is found to have an accumulation of frost or ice with a thickness of greater than or equal to 0.38 inches, a representative sample of 20 additional flow passages from the same bay shall be visually inspected. If these additional flow passages are found acceptable, the surveillance program may l proceed considering the single deficiency as unique and accept-able. More taan one restricted flow passage per bay is evidence of abnormal degradation of the ice condenser.
, c. At least once per 40 months by lifting and visually inspecting the l accessible portions of at least two ice baskets from each 1/3 of the t ice condenser and verifying that the ice baskets are free of detri-l mental structural wear, cracks, corrosion or other damage. The ice baskets shall be raised at least (12) feet for this inspection. O W-ICE CONDENSER 3/4 6-36E JAN 15 ISSO l uf
- . . . ..- . - . - _ _ . _.. - : T - :..-.
CONTAINMENT SYSTEMS ICE BED TEMPERATURE MONITORING SYSTEM LIMITING CONDITION FOR OPERATION 5
- 3. 6. 7. 2 The ice bed temperature monitoring system shall be OPERABLE with at least 2 OPERABLE RTD channets in the ice bed at each of 3 basic elevations
(/t'e ~, ye'9"and 4 5-'above the floor of the ice condenser) for each one third of the ice condenser. APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: ,
- a. With the ice bed temperature monitoring system inoperable, POWER OPERATION may continue for up to 30 days provided:
- 1. The ice compartment lower inlet doors, intermediate deck doors, and top deck doors are closed;
- 2. The last recorded mean ice bed temperature was less than or equal to 20*F and steady; and
- 3. The ice condenser cooling system is OPERA 8LE with at least:
a) 21 OPERABLE air handling units, b) 2 OPERABLE glycol circulating pumps, and c) 3 OPERABLE refrigerant units; Othetvise, be in at least HOT STANDBY within 6 hours and in COLO SHUTDOWN within the following 30 hours.
- b. With the ice bed temperature monitoring system inoperable and with the ice condenser cooling system not satisfying the minimum compo-nents OPERABILITY requirements of a.3 above, POWER OPERATION m3y continue for up to 6 days provided the ice compartment lower inlet doors, intermediate deck doors, and top deck doors are closed and the last recorded mean ice bed temperature was less than or equal to 15'F and steady; otherwise, be in at least HOT STANOBY within the next 6 hours and in COLO SHUTDOWN within the following 30 hours.
SURVEILLANCE REQUIREMENTS 5 4.6 J.2 The ice bed temperature monitoring system shall be determined OPERABLE by performance of a CHANNEL CHECK at least once per 12 hours. PICECONOENSER 3/4 6-379 JAN 151979 3.T B
CONTAINMENT SYSTEMS l ICE CONDENSER 000RS LIMITING CONDITION FOR OPERATION C , 3.6.7.3 The ice condenser inlet coors, intermeciate deck doors, and top deck l doors shall be closed and OPERABLE. APPLICA8ILITY: MODES 1, 2, 3 and 4 l ACTION: With one or more ice condenser doors open or otherwise inoperable, POWER OPERATION may continue for up to 14 days provided the ice bed temperature is monitored at least once per 1 hours and the maximum ice bed temperature is maintained less than or equal to 27*F; otharwise, restore the doors to their closed positions or OPERABLE status (as applicaole) within 48 hours or be in at least HOT STAN08Y within the next 6 hours and in COLD SHUT 00WN within the following 30 hours. SURVEILLANCE REOUIREMENTS s 4.6.7.3.1 Inlet Doors - Ice condenser inlet doors shall be: O
- a. Continuously monitored and determined closed by the inlet door position monitoring system, and
- b. Demonstrated OPERA 8LE during shutdown at least once per 3 months during the first year after the ice bed is fully locded and at least once per 6 months thereafter by:
- 1. Verifying that the torque required to initially open eacn door is less than or equal to (675) inch pounds. ,
- 2. Verifying that opening of each door is not impaired by ice, frost or debris.
- 3. Testing a sample of at least 25% of the doors and verifying that the torque required to open each door is less than (195) inch pounds when the door is (40) degrees open. This torque is defined as the " door opening torque" and is igual to the nominal door torque plus a frictional torque component. The doors selected for determination of the " door opening torque" shall l
be selected to ensure that all doors are tested at least once during four test intervals. O W-ICE CONDENSER 3/4 6 ,385 MAR 15 tgja 3&/T l l l l
CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- 4. Testing a sample of at least 25% of the doors and verifying that the torque required to keep each door from closing is greater than 78 inch pounds wten the door is 40 degrees open.
This torque is defined as the door closing torque" and is equal to the nominal door torqLe minus a frictional torque component. The doors selected for determination of the " door closing torque" shall be selected to ensure that all doors are tested at least once during four test intervals.
- 5. Calculation of the frictional torque of each door tested in accordance with 3 and 4, above. The calculated frictional torque shall be less than or equal to 40 inch pounds.
- 4. 5.,7. 3. 2 Intermediate Deck Doors - Each ice condenser intermediate deck door shall be:
- a. Verified closed and free of frost accumulation by a visual inspection at least once per 7 days, and
- b. Demonstrated OPERABLE at least once per 3 months during the first year after the ice bed is fully loaded and at least once per 18 O months thereafter by visually verifying no structural deterioration, by verifying free movement of the vent assemolies, and by ascertain-ing free movement when lifted with the applicable force shown below:
Door Lifting Force
- 1. d.%. r .- cr.we. na// <
37, y 3g,, pc:,, .i , +A seer .nijar aJ
- 2. tv crune we. H $ 33 7 1bs.
- 3. N in.nf h- cea% met we// $ 3 /. F lbs.
m;,.,i w n .tco-4.'.1<%. e A- cen:%'a, .n+ W't N < Nf 1bs. 5
- 4. 6.,7. 3. 3 Top Deck Doors - Each ice condenser top deck door shall be deter-mined closed and OPERABLE at least once per 92 days by visually verifying:
- a. That the doors are in place)(; and
- b. That no condensation, frost, or ice has formed on the doors or blankets which would restrict their lifting and opening if required.
O W-ICE CONDENSER 3/4 6-395 MAR 151973 359 mi-mi ii iiu
CONTAINMENT SYSTEMS INLET 000R POSITION MONITORING SYSTEM LIMITING CONDITION FOR OPERATION T
- 3. 5.7. 4 The inlet door position monitoring system shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3, and 4. ACTION: With the inlet door position monitoring systam inoperaola, POWER OPERATION may continue for up to la days, provided the ice bed temcerature monitoring system is OPERABLE and the maximum ice bed temperature is less than or ecual to 27*F when monitored at least once per 4 hours; otherwise, restore tne inlet coor position monitoring system to CPERABLE status within 48 hours or be in at least HOT SHUTD0hN within the next 6 hours and in COLD SHUTCC%N within the following 30 hours. SURVEILLANCE REOUIREMENT 4.6.7.4 The inlet door position monitoring system shall be determined OPERABLE by:
- a. Performing a CHANNEL CHECK at lea'.c once per 12 i y w:d.;-
7 ' 4"' - " '"J a hw r.> q ttee m rm :n b ao, !(Ze .- ca , .u,- c B /d it r,
- b. Performing a TRIP ACTUATING DEVICE OPERATIONAL TEST at least once per 18 months, and i l
- c. }
Verifying that the monitoring system correctly indicates the status of each inlet door as the door is opened and reclosed during its / testing per Specification 4.6.7.3.1. / 3^ J cp ,, " a /.:rm en & cci,he/ r e e *rr ~m " 4 / *' ~ lN ' cF f4e .:ys fe rn . O W-ICE CONDENSER 3/4 6 .40B' SEP I 51581 3& F
l CONTAINMENT SYSTEMS DIVIDER BARRIER PERSONNEL ACCESS DOORS AND EOUIPMENT HATCHES LIMITING CONOITION FOR OPERATION
.S*
- 3. 6.7. 5 The personnel access doors and equipment hatches between the contain-ment's upper and lower compartments shall be OPERABLE and closed.
APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: With a personnel acct door or equipment hatch inoperable or open except for personnel transit entry, restore the door or hatch to OPERABLE status or to its closed position (as applicable) within 1 hour or be in at least HOT , STANOBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. SURVEILLANCE REQUIREMENTS O ,
- 4. 6.,7. 5.1 The personnel access doors and equipment hatches between the con-tainment's upper and lower compartments shall be determined closed by a visual inspection prior to increasing the Reactor Coolant System T,yg above 200*F and after each personnel transit entry when the Reactor Coolant System T,yg is above 200*F.
5 4.6.7.5.2 The personnel access doors and equipment hatches between the con-tainment's upper and lower compartments shall be d'ttermined OPERABLE by visually inspecting the seals and sealing surfaces of these penetrations and verifying no detrimental misalignments, cracks or defects in the sealing surfaces, or apparent deterioration of the seal material:
- a. Prior to final closure of the penetration each time it has been opened, and
- b. At least once per 10 years for penetrations containing seals fabri-cated from resilient materials.
O PICECONDENSER 3/4 6-ns g JUN 1 3 79 ,
l l l CONTAINMENT SYSTEMS
/
\ CONTAINMENT AIR RECIRCULATION SYSTEMS ,/
\LIMITING CONaITION FOR OPERATION '
/
s - 3.6.7.6 Two. independent containment air recirculation systems shall be OPERABLE. APPLICABILITY: MCOES 1, 2, 3 and 4 i
/
ACTION: /
/
With one containment air recirculation system inopeedble, restore the inocerable system to OPERASLE status within 72 hours or be in at least HOT STAND 8Y within the next 6 hours ' in COLD SHUTDOWN within the,following 30 hours.
/
f
/
SURVEILLANCE RECUIREMENTS '
/ '
4.6.7.6 Each containment air recir/culation sy\ stem shall be demonstrated OPERABLE at least once per 92 d,ay's on a STAGGER TEST 3 ASIS by:
- a. Verifying that the/ return air fan starts on an auto-start signal after a 10 t 1,yir'nute delay and operates forN at least 15 minutes.
Verifying that with the return air fan damper \ closed, tne fan motor l b. I current is / t amps when the fan speed i ! RPM.
< s
- c. Verifyintj that with the fan off, the return air fahdamper opens when a' force of less than or equal to i
! counterweight. lbs is acp\lied to the l /
- d. Verifying that the motor operated valve in the suction line to the dontainment's lower compartment opens after a 10 1 minute delay.
- e. y c e- E-
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W-ICE CONDENSER JUL 15 378 l
l l l CONTAINMENT SYSTEMS CONTAINMENT AIR RETURN AND HYDROGEN SKIMMER SYSTEM LIMITING CONDITION FOR OPERATION 3.6.5.6 Two indepencent trains of the containment air return and hydrogen skimmer system shall be OPERABLE. l APDLICABILITY: MODES 1, 2, 3 and 4. i ACTION: l With one train of the containment air return and hydrogen skimmer system inoperable, restore the inoperable train to OPERABLE status within 72 hours or De in at least HOT STANDBY within the next 6 hours and in COLD SHUT 00WN within
- ne following 30 hours.
t SURVEILLANCE REOUIREMENTS 4.6.5.6 Eaca train of the containment air return and hydrogen skimmer system f.,, shall be demonstrated OPERA 8LE: 4-
- a. At least once per 92 days on a STAGGERED TEST BASIS by:
- 1. Verifying that the air return and hydrogen skimmer fans start automatically on a containment pnase 8 isolation (S ) test signal after a 9 1minutedelayandoperatefora3least15 minutes.
- 2. Verifying that during air return far, operation with the air return fan damper closed and with the. bypass dampers open, the fan motor current is less than or equal to 32 amps when the fan speed is 870 ; 30 rpm.
- 3. Verifying that with the hydrogen skimmer fan operating and the motor operated valve in its suction line closed, the fan motor current is less than or equal to 21.5 amps when the fan speed is 3599 + 20 rpm.
- 4. Verifying that with the air return fan off, the motor operated damper in the air return fan discharge line to the contain-ment's lower compartment opens automatically with a 10 + 1 second delay after a containment phase B isolation (S ) test signal. p
.s McGUIRE - UNIT 1 3/4 6-38 5 u ti r 7 1
( i _d CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- 5. Verifying that with the air return fan operating, the check damper in the air return fan discharge line to the contain-ment's lower compartment is open.
- 6. Verifying that the motor operated valve in the hydrogen skimmer suction line opens automatically and the hydrogen skimmer fans receive a start permissive signal.
- 7. Verifying that with the fan off, the return air fan check damper is clo, sed.
- s. At least once per 18 months by verifying that each air return fan and hydrogen skimmer fan is prevented from starting by the Contain-ment Pressure Control System when the containment internal pressure is less than or equal to 0.25 psid relative to the outside atmosphere.
]
l l { k McGUIRE - UNIT 1 3/4 6-39 # MNW L
CONTAINMENT SYSTEMS s FLOOR DRAINS l LIMITING CONDITION FOR OPERATION i 7
- 3. 6.,7. 7 The ice condenser floor drains shall be OPERABLE.
APPLICA3ILITY: MCDES 1, 2, 3 and 4 l ACTION: I With the ice condenser floor drain inoperable, restore the floor drain to OPERABLE status prior to increasing the Reactor Coolant System temperature above 200*F. l SURVE!t. LANCE REOUIREMENTS T
- 4. 6.,7. 7 Each ice condenser floor drain shall be demonstrated OPERABLE at least once per 18 months during shutdown by:
- a. Verifying that valve gate opening is not impaired by ice, frost or debris,
- b. Verifying that the valve seat is not damaged,
- c. Verifying that the valve gate opens when a force of less than or equal to 60 lbs is applied, and
- d. Verifying that the drain line from the ice condenser floor to the containment lower compartment is unrestricted.
W-ICE CONDENSER 3/4 6-4afI II E Ar#
~, w - m_ma,__
CONTAINMEN* SYSTEMS , REFUELING CANAL ORAINS LIMITING CONDITION FOR OPERATION l 6'
. 3.6.7.8 The refueling canal drains shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3, and 4. ACTION: With a refueling canal drain inoperable, restore the drain to OPERABLE status within one hour or be in at least HOT STANOBY within the next 6 hours and in
+ at least COLD SHUTDOWN within the following 30 hours.
SURVEILLANCE REQUIREMENTS
.5~
4.6/.8 Each refueling canal drain shall be demonstrated OPERABLE.
- a. Prior to increasing the Reactor Coolant System temperature above 200*F after each partial or complete filling of the canal with water by verifying that the pkg ' . ;.T.;,;;d fcu. ;M a &s 44ee and that the drain is not obstructed by debris, and
- b. At least once per 92 days by verifying, through a visual insoec-
-- - " /
tion, that "- ' - " there is no debris that / could obstruct the drain. /
/
/
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l l l l 9 W _-ICE CON 0EMSER 3/4 6.4Mr Aug 7 1980 h/ 3
h O CONTAINMENT SYSTEMS DIVIDER BARRIER SEAL LIMITING CONDITION FOR OPERATION i'
- 3. 6./. 9 The divider barrier seal shall be OPERABLE.
APPLICA8ILITY: MODES 1, 2, 3 and 4. ACTION: With the divider barrier seal inoperable, restore the seal to OPERA 8LE status prior to increasing the Reactor Coolant System temoerature above 200*F. SURVEILLANCE REOUIREMENTS
.f i
- 4. 6.,7. 9 The divider barrier seal shall be determined OPERABLE at least once per 18 months during shutdown by:
- a. Removing two divider barrier seal test coupons and verifying that the physical properties.of the test coupons are within the acceptable range of values shown in Table 3.6-3.
- b. Visually inspecting at least (95) percent of the seal's entire length and:
'" 1. Verifying that the seal and seal mounting bolts are properly installed, and
- 2. Verifying that the seal material shows no visual evidence of deterioration due to holes, ruptures, chemical attack, abrasion, radiation damage, or changes in physical appearances.
O W-ICE CONDENSER 3/4 6-4Mr M I g 37, 9 S
~'~~___-___-__-______-__________-_____-___-__-____--
TABLE 3.6-3 ! If ' M DIVIDER BARRIER SEAL "1 ACCEPTABLE PitYSICAL PROPERTIES 4 g i: y Menkun, 7 Tensile M j "a M t'e ri a l, N,,, ,,,,_
Strength Elop,r,iatiorv 5
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CONTAINMENT SYSTEMS N 3/416.8 VACUUM RELIEF VALVES (OPTIONAL) N
'N '
LIMITING CONDITION FOR OPERATION 3.6.8 The primary containment to atmosphere vacuur' relief valves shall be OPERABLE with an actuation set point of less than' or equal to psid.
/
APPLICABILITY: MODES tx 2, 3 and 4. ACTION: 's / N / Witn one primary containment tosatmosphere vacuum relief valve inoperable, restore the valve to GPERABLE status within 4 hours or be in at least HOT STANDBY within the next 6 hours andsin COLD SHUTDOWN within the following 30 hours. x
's SURVEILLANCE REOUIREMENTS
, N, 4.6.8 No . additional Surveillance Requirements otner than [h'ose required by Specification 4.0.5.
'x O
W-ICE CONDENSER ((6-4[B- JUN 1 1979
1 3/4.7 PLANT 3YSTEMS ! 3/4.7.1 TURBINE CYCLE SAFETY VALVES LIMITING CONDITION FOR OPERATION 4 3.7.1.1 All main steam line code safety valves associated with each steam
. generator Of :n uni:ohtet reac.or usukat k:p shall be OPERABLE with lift settings as specified in Table 3.7-3.
APPLICABILITY: MODES 1, 2 and 3. ACTION: u
- a. With (17) reactor coolant loops and associated steam generators in operation and with one or more main steam line coce safety valves inoperable, operation in MODES 1, 2 and 3 may proceed provided, that
>itnin 4 hours, either the inoperable valve is restored to GPERABLE O tatus or the Power Range Neutron Flux High Trip Setpoint is reduced V per Table 3.7-1; otherwise, be in at least HOT STANOBY within the next 6 hours and in COLD SHUTOOWN within the following 30 hours.
3
- b. With Fam&) reactor coolant loops and associated steam generators in operation and with one or more main steam line code safety valves associated with an operating loop inoperable, operation in MODES 1, 2 and 3 may proceed provided, that within 4 hours, either the '
ir. operable valve is restored to OPERABLE status or the Power Range Neutron Flux High Trip Setpoint is reduced per Table 3.7-2; otherwise, be in at least HOT STANOBY within the next 6 hours and in COLD SHUTOOWN within the following 30 hours.
- c. The provisions of Specification 3.0.4 are not applicable.
1 SURVEILLANCE REQUIREMENTS
- 4. 7.1.1 No additional Surveillance Requirements other than those required by Specification 4.0.5.
O W-STS 3/4 7-1 MAR 151979
5 TABLE 3.7-1 MAXIMUM ALLGVABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH IN0PERA8LE STEAM LINE SAFETY VALVES OURING # LOOP OPERATION 4'- Maximum Number of Incoersole Maximum Allowable Power Range Safety Valves on Any Neutron Flux High Setpoint Ooerating Steam Generator (Percent of RATED THERMAL POWER) l 1 (87) 2 (54) 4f 3 (4E) F 3 1 TABLE 3.7-2 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH INOPERA8LE STEAM LINE SAFETY VALVES OURING #4 LOOP OPERATION 3 Maximum Number of Inoperable Maximum Allowable Power Range Safety Valves on Any Neutron Flux Hign Setpoint Coeratino Steam Generator *_ (Percent of RATED THERMAL POWER) 1 3 g &/ 2 .C38) '/ f l 3 M 36 "At least two safety valves shall be OPERABLE on the non-operating staam generator. O
'f-STS 3/4 7-2 MAR 151973 l
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l l l PLANT SYSTEMS AUXILIARY FEECWATER SYSTEM LIMITING CONDITION FOR OPERATION
- 3. 7.1. 2 At least three independent steam generator auxiliary feedwater pumos and associated flow paths shall be OPERABLE with:
- a. No motor-driven auxiliary feecwater pumps, each capable of being powered from separate emergency busses, and
- b. One steam turbine-driven auxiliary feedwater pump capable of being powered from an CPERABLE steam supply system. .
AF/LICA8ILITY: MODES 1, 2, and 3. ACTION:
- a. With one auxiliary feedwater pump inoperable, restore the required auxiliary feedwater pumps to OPERABLE status within 72 hours or be in at least HOT STAND 8Y within the next 6 hours and in HOT SHUTDOWN within the following 6 hours.
- b. With two auxiliary feedwater pumps inoperable, be in at least HOT STANDBY witin 6 hours and in HOT SHUTCOWN within the following 6 hours.
- c. With three auxiliary feedwater pumps inoperable, immediately initiate corrective action to restore at least one auxiliary feedwater pump to OPERABLE status as soon as possible.
SURVEILLANCE REOUIREMENTS 4.7.1.2 Each auxiliary feedwater pump shall be demonstrated OPERA 8LE:
- a. At least once per 31 days by:
- 1. Verifying that each motor driven pump develops a discharge i pressure of greater than or equal to /2/C psig at a flow of !
greater than or equal to W4 gpm. l
- 2. Verifying that the steam turbine driven pump develops a discharge ,
pressure of greater than or equal to /.1/C psig at a flow of l greater than or equal to 90c gpm when the secondary steam l supply pressure is greater than W C psig. The provisions of ! Specification 4.0.4 are not applicaole for entry into MODE 3. PSTS 3/4 7-4 AUG 7 580 i l
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- 3. Verifying that each non-automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in its correct position.
4 Verifying that each automatic valve in the flow path is in the fully open position whenever the auxiliary feedwater system is placed in automatic control or when above 10% RATED THERMAL POWER.
- b. At least once per 18 months during shutdown by:
- 1. Verifying that each automatic valve in the flow path actuates to its correct position upon receipt of an auxiliary feeowater actuation test signal.
- 2. Verifying that each auxiliary feedwater pump starts as designed automatically upon receipt of an auxiliary feedwater actuation test signal.
f s ynke in suc/in, Me <,*
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ne ve/w t c,rerer ftrs rv sur c etc/. O W-STS 3/4 7-5 jul 2 31980 EmM ' . _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ . - _ . __ - _ . - _ . . -
6 PLANT SYSTEMS /
/
CONDENSATE STORAGE TANK /
,/
LIMITING CONDITION FOR OPERATION '
\
\
3.7.1.3 'The condensate storage tanx (CST) shall be OPERABLE with a contained water volume of at least gallons of water.
\ e' APPLICA8ILITW s MODES 1, 2, and 3.
/
N ACTION: \ With the condensateystorage tank inoperable, within 4 hours either:
- a. Restore the' CST to OPERABLE status or be in at least HOT STANDBY within the next 6 hours and in HOT SHUTDOWN within the following 6 hours, or
- b. Demonstrate the 0PERASILITY of the (alternate water source) as a backup supply,to the auxiliary feedwater pumps and restore the condensate storage tank to OPERABLE status within 7 days or be in at least HOT STAN08Y within the next 6 hours and in HOT SHUTDOWN within the following 6 hours. s
/
SURVEILUNCEREQbIREMENTS
/ .
4.7.1.3.1/The condensate storage tank sh 1 be demonstrated OPERABLE at least once per ,T2 hours by verifying the contain water volume is within its liitts when th/ tank is the supply source for the a iliary feedwater pumps. 4.7.1 .2 The (alternate water source) shall be demonstrated OPERABLE at leas,t on.ce per 12 hours by (method dependent upon alternate source) whenever s th/ (alternate water source) is the supply source Yor the auxiliary feedwater pumps. \ k O PSTS 3/47.r JUL 2 31980 ,
O PLANT SYSTEMS ACTIVITY LIMITING CONDITION FtR OPERATION 2 3.7.1.# The specific activity of the secondary coolant system shall be less than or equal to 0.10 microcuries/ gram DOSE EQUIVALENT I-131. ! APPLICABILITY: MODES 1, 2, 3, and 4. ACTION: With the specific activity of the secondary coolant system greater than 0.10 microcuries/ gram COSE EQUIVALENT I-131, be in at least HOT STANO3Y within 6 hours and in COLD SHUTDOWN within the following 30 hours. l lO ! SURVEILLANCE REOUIREMENTS ! 3 l 4.7.1.# The specific activity of the secondary coolant system shall be i determined to be within the limit by performance of the sampling and analysis i program of Table 4.7-1. I l O PSTS 3/4 7 ,7 6 15 373
O TABLE 4.7-1 SECONDARY CCOLANT SYSTEM SPECIFIC ACTIVITY 5 AMPLE AND ANALYSIS PROGRAM T/PE OF MEASUREMENT SAMPLE AND ANALYSIS AND ANALYSIS FREOUENCY l l
- 1. Gross Activity Determination At least once per 72 hours.
- 2. Isotopic Analysis for DOSE a) 1 per 31 days, wnen-EQUIVALENT I-131 Concentration ever the gross activity determination indicates iodine concentrations greater than 10% of the allowable limit.
- 3) 1 per 6 months, wnen-ever the gross activity determination indicates iodine concentrations below 10% of the allow-able limit.
O W-STS . 3/4 7-g 7 MAY 151976 1
e O PLANT SYSTEMS MAIN STEAM LINE ISOLATION VALVES LIMITING CONDITION FOR OPERATION w 3.7.1.5 Each main steam line isolation valve shall be OPERABLE. APPLICABILITY: MODES 1, 2, and 3. l ACTION: MODE 1 - With one main steam line isolation valve inoperable but open, POWER OPERATION may continue provided the inocerable valve is restored to OPERABLE status within 4 hours; otherwise reduce power to less than or equal to 5 percent of RATED THERMAL POWER witnin 2 hours. MODES 2 - With one main steam line isolation valve inoperable, subsequent and 3 cperation in MODES 2 or 3 may proceed provided:
- a. The isolation valve is maintained closed.
l b. The provisions of Specification 3.0.4 are not applicable. Otherwise, ce in HOT STANDBY within the next 6 hours and in HOT SHUTDOWN within the following 6 hours. SURVEILLANCE REQUIREMENTS s l 4.7.1.E Each main steam line isolation valve shall be demonstrated OPERABLE ! by verifying full closu p within f/ve seconds when tested pursuant to Specification 4.0.5. O W-STS 3/4 7-7 7 AUG o 19 8 !
. ~_ _ _ _ .
-,er, ----eu--w gu- ---'----z ---w w+-- + - -m-- ', e - - - ' y ---- r--- ==
PLANT SYSTEMS 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION LIMITING CONDITION FOR OPERATION 3.7.2 The temperatures of both the primary and secondary coolants in the steam generators shall be greater than (70)*F when the pressure of either coolant in the steam generator is greater than (200) psig. APPLICABILITY: At all times. ACTIdN: With the requirements of the above specification not satisfied:
- a. Reduce the steam generator pressure of the applicable side to less than or equal to (200) psig within 30 :ninutes, and
- b. Perform an engineering evaluation to determine the effect of the overpressuri::ation on the structural integrity of the steam generator.
Determine that the steam generator remains acceptable for continuea operation prior to increasing its temperatures above 200*F. SURVEILLANCE RE0VIRE1ENTS O 4.7.2 The pressure in each si 6 of the steam generator shall be determined to be less than 200 psig at least once per hour when the temperature of either the primary or secondary coolant is less than 70*F. O W-STS 3/47-16 9 JUN 1 1979
t PLANT SYSTEMS l 3/4.7.3 COMPONENT COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.3 At least two independe.at component cooling water loops sna11 be OPERA 8LE. APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: l With only one component cooling water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours or be in at least HOT STAND 8Y within the next 6. hours and in COLD SHUTDOWN within the following 30 hours. SURVEILLANCE REOUIREMENTS 4.7.3 At least two component cooling water loops shall be demonstrated OPERABLE:
- a. At least once per 31 days by verifying that each valve (manual, l
power operated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.
- b. At ieast once per 18 months during shutdown, by verifying that eacn automatic valve servicing safety related equipment actuates to its correct position on a u test signal.
Sakty xpcNen (Sd O PSTS 3/4 7-JI /# _ _ . _ _ . . _ . _~ ._ _-
PLANT SYSTEMS 3/4.7.4 SERVICE WATER SYSTEM LIMITING CONDITION FOR OPERATION nuclwr 3.7.4 At least two independentjservice water loops shall be OPERA 8LE. APPLICA8ILITY: MODES 1, 2, 3 and 4 ACTION: With only one service water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours or be in at least HOT STANOBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. SURVEILLANCE REOUIREMENTS ! 4.7.4 At least two service water loops shall be demonstrated OPERABLE:
- a. At least once per 31 days by verifying that each valve (manual, power operated or autcmatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.
- b. At least once per 18 months during shutdown, by verifying that each automatic valve servicing safety related equipment actuates to its correct position on a u test signal.
F Ski y by'e<!N,,(E,) l l W-STS 3/4 7-3t // MAY 151975
l l l l ( \ 1 PLANT SYSTEMS j 3/4.7.5 STANDSY NUCLEAR SERV,If .TER PONO LIMITING CONDITION FOR OPERATION l 3.7.5 The standby nuclear service water pond shall be OPERABLE with:
- a. A minimum water level at or above elevation 739.5 feet Mean Sea Level, USGS datum, and
- b. A water temperature of less than or equal to 78*F at elevation 700 feet in the intake structure.
APPLICABILITY: MODES 1, 2, 3 and 4. [7Mim ACTION: ('..tp/ni y to .k M W^lfs'-) ' With the requirements of the above specification not satisfied, be in at least riot STANDBY within 6 hours and in COLD SHUTDOWN within the following 30 hours. 1 (\ SURVEILLANCE REQUIRMENTS 4.7.5 The standby nuclear service water pond shall be determined OPERABLE:
- a. At least once per 24 hours by verifying the water level to be within its limit.
- b. At least once per 24 hours during the months of July, August and September by verifying the water temperature to be within its ifmit.
- c. At least once per 12 months by visually inspecting the dam and i verifying no abnormal degradation, erosion, or excessive seepage.
l r McGUIRE - UNIT 1 3/4 7-J3 /1
, U N r T 2- ~ _ _ . . - ._____-_ - . . _____ - __ -_
l .. ... _.. . -
/
/
' PLA TMYSTEMS / 5744py rWcu4,f uft M k& W / 'R s<P 3/4.7.5 \e.TIMATE "E.'? SI= ' OPTIONAL-)- / LIMITING CONDITi N FOR OPERATION ggi,s.4 o r mic.: wN/N'"' 3.7.5 The "*'---- k-+~ " shall be OPERABLE with: a.
\ / 73W. f M A minimum wate level at or above elevation (j ) Mean Sea Level, USGS datum, and
- b. Amenepege water te. erature of less than or equal to (79)"F. -r"-
n h w f4s* 7T f
/ S i;,hhe s-hwafar.,_ ,
- APPLICABILITY: MODES 1, , 3 and .
ACTION: With the requirepents of the above specif1 ation not satisfied, be in at least HOT STANOBY wittlin 6 hours and in COLD SHUTDOWN within the following 30 hours. i l N\ SURVEI ANCE REQUIRMENTS \ ls6-w ,,,/,,,, p , , y,; e e4r pw / \
.7.5 The dtf::t; heat-4i44 shall be determined OPERABLfet h st once mer 2 imur= Ly
/.-w,itMn--the tr_1imiverifyhg-the average w:ter-temperature-and-wathek-leve N 's l N 's f<!,9< '
s.in cm/ : I , I i l O W-STS 3287 4 . SEP 25 ma l
1 [ ? / 0 PLANT SYSTEMS W4.7.6 FLOOO PROTECTION (OPTIONAL *) / LIMF7ING CONDITION FOR OPERATION 3.7.6
\Flood protection shall be provided for all safety related' / systems, ccaponent's,and structures when the water level of the (.u'sually the ultimate heat sink) exceeds _ Mean Sea Level USGS catum; at .
\
APPLICA8ILITYL At all times. /
\ '
/
ACTION: \, ,.
\ /
With the water level at above elevation Mean Sea Level USGS datum:
- a. (3e in at least HOT STAND 8Y within S he'urs and in at least COLD SHUTOOWN within the following 30 hours) and D. Initiate and c molete within hours, the following flood protection measures:
- l. (Plant dependent)N'N
- 2. (Plant dependent) \
SURVEILLA.NCE RECUIREMENTS .
\\
\
k
\
4.7.6 The water level at. shall be determined to be within the limits by:
- a. Measurement elevation atonce ast Je/.per 24 hour when the
/ Mean Sea Level USGS datum, and water level is below
- b. Measurement at lea:t once per 2 hours when ghe water level is equal N to or abo elevation Mean Sea Level USGS datum.
- This 'cification not required if the facility design has acequate passive floo ontrol protection features sufficient to acconmodate the Design Basis Flo identified in Regulatorv Guide 1.59, August 1973. \
'N
/
?
O s
'f-STS g3/4 G-14~ NOV 151977
-. - . - _ . ..- - - - .2: -- . . - ..: ~ ~ ~ -
O G PLANT SYSTEMS , ,
. c.i , i.
3/4.7.7 CONTROL ROOM-EMEMENGY "" CL imd SYSTEM LIMITING CONDITION FOR OPERATION
& .,,a yed,% Mn 3.7.7 Two -independent control r;= ;nr;=cy W ch=up systems shall be l OPERABLE.
l l APPLICABILITY: ALL MODES IUN ACTION: ( .1 g /is.s i+ deM um*h.) MODES 1, 2, .i and 4: l With one control room emergency air cleanup system inoperable, restore the I inocerable system to OPERABLE status within 7 days or be in at least HOT l STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. MODES S and 6: a. atec wdh S.'sn With one control z ~ - .;.;. pin.y or ehrep systent inoperable, Oy restore the inoperable system to OPERABLE status within 7 days or initiate and maintain operation of the remaining OPERABLE control d ' "' Vor4% Wcn - x: ;=:y cir clea...i, system in the recirculation mode. aren ! b. With both control . ee ...venh%ih%..------ = d --"- s with the OPERABLE control rM'x=Y#5d["8?ystems inoperable, h rup system, or required to be in the recirculation mode by ACTION (a), not capable of being powered by an OPERABLE emergency power source, suspend all operations involving CORE ALTERATIONS or positive reactivity changes. SURVEILLANCE REQUIREMENTS l
& area venh%%
4.7.7 Each control m ;nc;;xy ai :h=;p system shall be demonstrated OPERABLE:
- a. At least once per 12 hours by verifying that the control room air temperature is less than or equal to (120)*F.
udw tia spnn an alm /y in t,ravh,%* l
- b. At least once per 31 daysAon a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 10 hours with the heaters % ln safeinci,*e end & Jun,/ddy cettfie//< r- s.:. f a f- /.o s > h'sr er- c.;ue! ,h 70$7-a fefc bE C U,n!k/ f*fe i-STS 3/4 7-yf / 3 JUL 2 71981
PLANT SYSTEMS SURVEILLANCE RECUIREMENTS (Continued)
- c. At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorcer housings, or (2) following I painting, fire or chemical release in any ventilation zone communicating with the system by:
I g g 6fyy'ing h tg 'em%r at a flo ~ 'of efaQ , and4xha ag t3rettg EPA # j - nd_cha 4dsorcersdthe' ,taYkypassifl,9 co't364 ity
~fent,jn'ckatfig-leakage tDrougn~ptyivsy f
*beesystem divertf. -valv .1 s less tha for equal t( K w' 's *e6testad'_ acmhtingy
~
cold'T,CP at the'syst ntak ror sys'_ _t ems-witM'iiiver2Wyv ->
/ 2: Verifying that the .eheaw- system satisfies the in-placa testing acceptance criteria and uses the test procedures of Regulatorf Positions C.S.a, C.5.c and C.S.d of Regulator / Guide 1.52, Revision 2, March 1978, and the system flow rate is Jer cfm 10%.
? . b. Verifying, within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulator /
Position C.6.a of Regulatorf Guide 1.52, Revision 2, March . 1378. 3 . 4t Verifying a system flow rate of Occ cfm + 10% during system aceration when tested in accordance with ANSI N510-1975.
- d. After every 720 hours of charcoal adsorber operation by verifying within 31 days after removal, that a laboratory analysis of a represen-tative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.
- e. At least once per 18 months by:
- 1. Verifying that the pressure drop across the combined _HEPA _ p g-filters and charcoal adsorber banks is less than M inenes Water Gauge while operating the system at a flow rate of .2cco cfm + 10%.
- 2. Verifying that on a containment phase A isolation test signal, the system automatically switches into a recirculation mode of operation with flow throtgh the HEPA filters and charcoal adsorber banks. //
,, / 9
- 3. Verifying that the system maintains thet ontrol room at a positive pressure of greater than or equal to ( .
inen W.G. relative to the outside atmosphere during system operation. We
- 4. Verifying that the,(heaters dissipate /e C' + /. C kw when _
tested in accordance with ANSI N510-1975. W-STS 3/4 7-W 15 W
- __ _ _ , =. . . _ _ .
J PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- f. After each complete or partial replacement of a HEPA filter bank by i verifying that the HEPA filter banks remove greater than or equal to (99.95)%" of the 00P when they are tested in place in accordance with ANSI N510-1975 while operating the system at a flow rate of '
Mrc- cfm +_ T CL l g. After each complete or partial replacement of a charcoal adsorber bank by. verifying that the charcoal adsorbers remove greater than or equal to 99.95% o.f a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI NS10-1975 while operating the system at a flow rate of i cec cfm : 1CL I O L l
- - /
99d5 analy,Yva'pplicab1 M g 61ter f ci ae[ e-taf{ty-ses{9gwhen 11ter ficf y ofe is,, dume , 3/4 7- # / C w-STS MAY 151980
j 4/*C l Pl. ANT SYSTEMS l
'\3/4.7.8 ECCS PUMP ROOM EXHAUST AIR CLEANUP SYSTEM l
'N LIMITING CONDITICN FOR OPERATION N
3.7.8 Two independent ECCS pump room exhaust air cleanup . stems shall be OPERABLE. \
\
APPLICA8ILITY: MODES 1, 2, 3 and 4.
\
ACTION:
\
With one ECCS pump room exhaust air cleanup sys em inoperable, restore the inoperable system to OPERABLE status within 7, ays or be in at least HOT STAN08Y within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. \
\
\
SURVEILLANCE REQUIREMENTS \ 4.7.8 Each ECCS pump room exhauy air Jeanup system shall be demonstrated , OPERABLE:
- a. At least once per } days on a STAGGERED TEST BASIS by initiating, from the control om, flow through the HEPA filters and charcoal adsorbers and ve ifying that the sys' tem operates for at least 10 hours with the eaters on.
- b. At least one per 18 months or (1) after(any structural maintenance ;
on the HEP filter or charcoal adsorber housings, or (2) following ! painting, ire or chemical release in anyNent11ation zone communic ing with the system by:
- 1. Verifying that with the system operatingsat a flow rate of
'fm + 10% and exhausting through the HEPA
\ filters and charcoal
, adsorbers, the total bypass flow of the sy(tem to the facility ; I vent, including leakage through the system diverting valves, is 1 less than or equal to 1% when the system is tested by admitting cold DOP at the system intake. (For systems w'ith diverting valves. )
- 2. Verifying that the cleanup system satisfies the }n place testing acceptance criteria and uses the test procedures of Regulatory i Positions C.S.a, C.5.c and C.S.d of Regulatory Gui'de 1.52, l Revision 2, March 1978, and the system flow rate is' cfm l
+ 10%.
O pSTS .M(7-38 ' MAY I 51990
\
g~/ ( PLANT SYSTEMS 3/4.7.7 AUXILIARY BUILDING FILTERED EXHAUST SYSTEM (ECCS PUMP ROCM EXHAUST AIR FILTRATION SYSTEM) LIMITING CONDITION FOR OPERATION 3.7.7 The auxiliary building filtered exhaust system shall be OPERABLE. APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: With the auxiliary builoing filtcred exhaust system inoperable, restore the system to CPERABLE status within 24 hours or be in at least HOT STANCBY within the next 6 hours and in COLD SHUTDOWN witnin the following 30 hours. SURVEILLANCE REOUIREMENTS 4.7.7 The auxiliary building filtered exhaust system shall be demonstrated OPERABLE:
- a. At least once per 31 days by initiating flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 15 minutes, s
- b. At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorcer housings, or (2) following painting, fire or chemical release in any ventilation zone _ -- .
communicating with the syste(m _ y,,'H*a" t t r""er u]J cc c j~ fc n (7.,.i W ("-'" nf - W<
- l. Verifying that with the' system operathg at a flow rate 7 54,000 cfm : 10% (both fans operatingf8and exhausting through the HEPA filters and charcoal adsorbers, the total bypass flow of the system to the facility vent, including leakage through the system diverting valves, is less than or equal to 1% when l the system is testad by acmitting cold 00P at the system intake.
- 2. Verifying that the system satisfies the in place testing acceptance criteria and uses the test procedures of Regulatory Positions C.S.a, C.S.c and C.S.d of Regulatory Guide 1.52, Revision 2, March 1978 (except for the provisions of ANSI N510 Sections 8 and 9), and the system flow rate is 54,000 cfm + 10%
(both fans operating).- v.;8 d cc 43,eccck y /ef, (~ (lcm &c 7 era /% f - m ;/ .t), V McGUIRE - UNIT 1 3/4 7->T /47 UNIT .2:
- - , - . - - - --a Sw l
p. m PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
. 3. Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accor-dt!.ce with Regulatory Position C.6.b of Regulatory Guide 1.52,
, Revision 2, March 1978, meets the laboratory testing criteria l of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.
- 4. Verifying a system flow rate of 54,000 cfm + 10% (both fans "dt #""/ )
er M.se e I e Pc y 2 g g .,*";} curing system operation when tesied in accordance
' aw r,, + </" - f with ANSI N510-1975.
- c. After every 720 hours of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of a repre-sentative carbon samole obtaineo in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laceratory testing criteria of Regulatory Position C.S.a of Regulatory Guice 1.52, Revision 2, Maren 1978.
- d. At least once per 18 months by:
1 '-
,, 1. Verifying that the pressure droo across tne combined HEPA (d \
filters and charcoal adsorcer banks of less than 6 inches Water Gauge wnile coerating the system at a flow rate of 54,000 cfm + 10% (both f ans operatingh-vaif /) er W ee e/- 4 // % - ( t.crA fair.r eferansy - M/r- 2 ) .
- 2. Verifying tnat the system starts automatically on a Safety Injection Test Signal and directs its exhaust flow througn the HEPA filters and charcoal adscreers.
- e. After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks reaove greater than or equal to 99.95% of the CCP wnen they are tested in place in accordance ,vith ANSI N510-1975 000-cfm + 10% (both wnilefans operating the system operating 5-6,r at
/) aerflow Wj rate e" : of
/c 54,X'
, (Acti friu cf u v1 % f - /4 1 + .1 ). I
- f. After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99.95% of a halogenated nycrocarbon refrigerant test gas when they are tested in place in accordance with ANSI N510-1975 while operating the system at a flow rate of 54,000 cfm + 10% (both l fans operatingf. - Mrif /) e,. y3, sec cS,., g /s ey.
(le t f %s op '<wr6*,ny - thrit 2 ) . ov 9 McGUIRE - UNIT 1 3/4 7-J6 /7 usM L
W WC e - PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
\, verifying within 31 days after removal that a laboratorydnalysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52,. Revision 2 March 1978, meets the laboratory testing criteria.of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1973. .
- 4. Verifying \a system flow rate of cfm + AGE during system operation when tested in accordance with ANSI M510-1975.
- c. After every 720 hours of charcoal adsorbep' operation by verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained ,in accordance with Regulatory Position C.S b of Regulatory Guide 1 752, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a Revisioi 2, March 1978.
of Regulatory Guide 1.52'N
- c. At least once per 18 months \b /
- 1. Verifying that the pressure drop across the combined HEPA filters and charcoal jidsorber banks of less than (6) inches o 2.
Water Gauge while efs + m. Verifying that Signal. rating.the system at a flow rate of x system starts on a Safety Injection Test
- 3. Verifying that the filter cooling. bypass valves can be manually
/
opened. \
\
- 4. Verifyin hat the heaters dissipatai 1 kw when tasted n accordance with ANSI M510-1975.
\
- e. After each complete or partial replacement of. a HEPA filter bank by verifying'that the hEPA filter banks remove greater than or equal to (99.95),%" of the DOP when they are tested in place in accordance with ANSI $510-1975 while operating the system at a flow rate of -
cfmg10%. \
/ \
- f. After each couplete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99.91i% of a halogenated hydrocarbon refrigerant test gas when they are tested in place in accordance with ANSI M510-1975 while operating the system at a flow rate of cfm 1 10%.
s 99.95% applicable when a filter efficiency of 99% is assumed in the safety analyses; 99% when a filter efficiency of 905 is assumed. N O Ld-STS 2f*"[ MAY 151980
S'uf4/~Ce - PLANT SYSTEMS 3/4.7.9 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.9 All snubbers listed in Tables 3.7-4a and 3.7-4b shall be OPERABLE. APPLICABILITY: MODES 1, 2, 3, and 4. (MODES 5 and 6 for snubbers located on systems recuired OPERACLE in those MODES.) l ACTION: With one or more snubbers inoperable, within 72 hours replace or restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.9.c on the supported component or declare the supported system inoperable and follow the appropriate ACTION statement for that system. SURVEILLANCE REGUIREMENTS 4.7.9 Each snubber shall be demonstrated OPERABLE by performanca of the following augmented inservice inspection program and the requirements of Specification 4.0.5.
- a. Visual Inscections The first inservice visual inspection of snubbers shall be performed after 4 months but within 10 months of commencing POWER OPERATION and shall include all snubbers listed in Tables 3.7-4a and 3.7-4b.
If less then two snubbers are found inoperable during the first inservice visual inspection, the second inservice visual inspection shall be performed 12 months 2 25% from the date of the first inspection. Otherwise, subsequent visual inspections shall be performed in accordance with the following schedule: No. Inoperable Snubbers Subsecuent Visual per Insoection Period Inscection Period *# 0 18 months + 25% 1 12 months 7 25% 2 6 months 7 25% 3,4 124 days 7 25% 5,6,7 62 days 7 25% 8 or more 31daysi25% The snubbers may be categorized into two groups: Those accessible and those inaccessible during reactor operation. Each group may be inspected independently in accordance with the above schedule.
"The inspection interval shall not be lengthened more than one step at a time.
#The provisions of Specification 4.0.2 are not applicable.
Ld-STS 3/4'[-20/ SE? I 61980 I l
-. - - . . . l l
l /fe~ . ReYcec/e cf PLANT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued)
- b. Visual Insoection Acceotance Criteria Visual inspections shall verify (1) tnat there are no visible indications of damage or impaired OPERABILITY, (2) attachments to the foundation or suoporting structure are secure, and (3) in those locations where snubber movement can be manually induced without disconnecting the snucber, that the snubber has freedom of movement and is not frozen up. Snubbers wnich appear inoperaole as a result of visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection interval, providing that (1) the cause of the rejection is clearly established and remedied for that particular snuober and for other snubbers that may be generically susceptible; and (2) tne affected snuober is functionally tested in the as found condition and determined OPERABLE per Soecifications 4.7.9.d or 4.7.9.e, as aoplicable. However, when a fluid port of a hydraulic snuboer is found to be uncovered tne snuccer snall ce declared inopersole and cannot ce aeterminec OPERA 3' E via functional testing for the purpose of establisning :ne next visual insoection interval. All snubbers connected to an incoerable common hydraulic fluid reservoir shall be counted as inoperaole snucbers.
- c. Functional Tests At least once per 18 months during shutdown, a representative sample g of at least (10% of the total of each type of snubber in use in the plant shall be functionally tested either in place or in a bench test.
For each snubber that doos not meet the functional test acceptance criteria of Specification 4.7.9.d or 4.7.9.e, an adcitional 10% of that type of snubber shall be functionally tested until no more failures are found or entil all snubbers have been functionally tested). or (that number of snubbers which follows the axoression 35 (1 + f), where c* is the allowable number of snubbers not meeting the a The value c will be arbitrarily chosen by the applicant and incorporated into the expressions for the representative sample and for the resample prior to the issuance of the Technical Specifications. The expressions are intended for use in plants with larger numbers of safety-related snubbers (>500) and provide a confidence level of approximately 95% that 90% to 100% of the snubbers in the plant will be OPERA 8LE within acceptable limits. That is, the confidence level will be Provided no matter what value is chosen for c. It is advised, however, that discretion be used when initially choosing the value for c because the lower the value of c (the lower the amount of snubbers in the representative sample), the higher the amount of snubbers required in the re-sample will be. To illustrate: If c = 2 and 3 snubbers are found not to meet the functional test acceptance criteria, there will be 70 snubbers in the representative sample and 31 snubbers required for testing in the re-sample; If c = 2 and 4 snubbers fail the functional test, there will be 70 snubbers in the representative sample and 62 snubbers required for testing in the re-sample; If e = 0 and 1 snubber fails e e functional test, O there will be 35 snubbers in the representative sample ud 140 snubbers required for testing in the re-sample; If : = 0 and 2 snubbers fail the functions test, there will be 35 snubbers in the representative samp.le ano 280 snubbers required for testing in the re-sample. PSTS 33 ypJ1- p., , ; g.g hirum -
&e Supetca A Y PLANT SYSTEMS PLANT SYSTEMS
, SURVEILLANCE RECUIREMENTS (Continued) acceptance criteria selected by the operator, shall be functionally tested either in place or in a bench test. For each number of snubbers above c which does not meet the functional test acceptance criteria of Specifications 4.7.9.d. or 4.7.9.e, an additional sample selectedaccordingtotheexpression35(1+j)(ef)2(a-c) 1 shall be functionally tested, where a is the total number of snubbers found inoperable during the functional testing of the representative sample. Functional testing shall continue according to the expression 2 b[35(1+j)(cl)2]wherebisthenumberofsnubbersfound inoperable in the previous re-samole, until no additional inoperable snubbers are found within a sample or until all snubbers in Table 3.7-4a and 3.7-4b have been functionally tested). The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of snubbers. At least 257,of the snubbers in the representative sample shall include snubbers frrm the following three categories:
- 1. The first snabber away from each reactor vessel nozzle,
- 2. Snubbers within 5 feet of heavy equipment (valve, pump, turbinte, motor, etc.),
- 3. Snubbers within 10 feet of the discharge from a safety relief valve.
Snubbers identified in Tables 3.7-4a and 3.7-4b as "Especially Difficult to Remove" or in "High Radiation Zones During Shutdown" shall also be included in the representative sample.* Tables 3.7-4a and 3.7-4b may be used jointly or separately as the basis for the sampling plan. In addition to the regular sample, snubbers which failed the previous functional test shall be ratested during the next test period. If a spare snubber has been installed in place of a failed snubber, then both the failed snubber (if it is repaired and installed in another position) and the spare snubber shall be retested. Test results of these snubbers may not be included for the re-sampling. Permanent or other exemptions from functional testing for individual snubbers in these categories may be granted by the Commission only if a justifiable basis for exemption is presented and/or snubber life destructive testing was perfurmed to qualify snubber operability for all design conditions at either the completion of their fabrication or at a subsequent date. pSTS 3(4' 7-%' gp 16 1989 i
5 k >_ $ WC44Y O PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) . If any snubber selected for functional testing either fails te lockup or fails to move, i.e., frozen in place, the cause will be evaluated and if caused by manufacturer or design deficiency, all snubbers of the same design subject to the same defect shall be functionally tested. This testing requirement shall be independent of the requirements stated acove for snubbers not meeting the functional test acceptance criteria. For the snubber (s) found inoperable, an engineering evaluation shall be performed on the components which are supported by the snuceer(s). The purpose of this engineering evaluation shall be to determine if the components supported by tne snucber(s) were adversely affected by the inoperability of the snuboer(s) in order to ensure tnat the supported component remains capable of meeting the designed service.
- d. Hvdraulie Snubbers Functional Test Acceotance Criteria The hydraulic snubber functional test shall verify that:
l 1. Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.
- 2. Snubber bleed, or release rate, where required, is within the specified range in compression or tensi n. For snubbers specifically required to not displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.
- e. Mechanical Snubbers Functional Test Acceptance Criteria The mechanical snubber functional test shall verify that:
- 1. The force that initiates free movement of the snuboer rod in either tension or compression is less than the specified maximum drag force. Drag force shall not have increased more than 50".
since the last surveillance test. l
- 2. Activation (restraining action) is achieved within the specified r
range of velocity or acceleration in both tension and compression.
- 3. Snubber release rate, where required, is within the specified range in compression or tension. For snubbers specifically required not to displace under continuous load, the ability of the snubber to withstand load without displacement shall be veri fied.
r$75 Sfw mov 2 o sso w -w- - v , - - v v
- . . - . . .. . . . ~. -.._
fst e- Sy W C* t'- PLANT SYSTEMS i SURVEILLANCE REQUIREMENTS (Continued)
- f. Snubber Service Life Monitoring A record of the service life of each snubber, the date at which the designated service life commences and the installation and mainte-nance records on which the designated service life is based shall be maintained as required by Specification 6.10.2.
Concurrent with the first inservice visual inscection and at least once per 13 months thereafter, the installation and maintenance records for each snubber listed in Tables 3.7-4a and 3.7-ab shall be reviewed to verify that the indicated service life has not been exceeded or will not be exceeded prior to the next schedulec ;cubber service life review. If the indicated service life will be exceeded prior to the next scheduled snubber service life review, the snucber service life shall be reevaluated or the snubber shall be replaced or reconditioned so as to extend its service life Oeyond the cate of the next scheduled service life review. This reevaluation, replacement or reconditioning shall be indicated in the records. O G
~
W-STS [/4 % g 2 01c80
PLANT SYSTEMS 3/4.7.8 SNUB 8ERS LIMITING CONDITION FOR OP2 RATION 3.7.8 All snubbers ' St:d '- TC:.; :.' 4 .... :.' 't shall be OPERABLE. APPLICABILITY: MODES 1, 2, 3, and 4 (MODES 5 and 6 for snumbers located on systems required CPERA3LE in those MODES.) ACTION: With one or more snubbers inocerable, within 72 hours replaca or restore the inoperacle snuteero', 0; ' up Of,7. per Soecificatich7.9.c PERABLE status and ;:erform n the supportad ccmconent or declare the succortec an engineering evaluation fd system inocerablep m wiiaw the acpropriata ACTICN statement for that systam.
. q,'~1. g (,
SURVEILLANCE REGUIRE.MENTS
- 4. 7. 3 Eacn snuceer sr.al' ce demenstratac OPERASLE by ;:erformance of the folicwing augmented insarvica inspection pr gra.m anc tne recuirements of Speci fication A.0.5. - -
gygpt.g 7~e } M*~ M ' A
- a. Visual Insoec: ions cwe447d h b 4##
] The fi
- service visual aftar a a nths but within spection of snubbers shall be cerformed months of comencing POWER OPERATION gov: and shall include all snu rs,': au m 7.L: n 2. 7 4. ww -MAb2---
"j g A 6 4_f If less then t a snumberspare found inoperable during the first inservica visual inspection, the second inservice visual inspection shall be performed 12 months t 25% frem the date of the first inscection. Otherwise, subsequent visual inspections shall be performed in accordance with the following schedule:
s
- r. Co-M h.'
,, ,,4 0 . Inoperable s D# Subsequent V -
"ena vA t
l j)opf ro w v D cer Insoection c Inscection { fe 0 18 months + 25% 1 12 months ; 25% 2 6 months 7 25% 3,4 124 days 25% 5,6,7 62 days % 25% 8 or more 31 days 7 25% I The snubbers may be categorized into two groups: Those accessible A77AC87Y'gyr' ' and those inaccassible dering reactor operation. Each group may be
'n" inspected independently in accordance with the above schedule.
D h v
"The inspection interval shall not be lengthened more than one step at a time O unless a generic problem has been identified and corrected; i~n that event the inspection may be lengthened one step the first time and two steos thereafter if no inoceracle snuobers are found.
#The provisions of Specification 4.0.2 are not applicacle.
McGUIRE - UNIT 1 3/4 7-y1 l uN.t r 1 M A
g .., PLANT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued)
- b. Visual Insoection Acceotance Criteria Visual inspections shall verify (1) that there are no visible indica-tions of damage or impaired OPERABILITY, (2) attachments to the foundation or suoporting structure are secure, and (3) for mechanical snuobers where snucber movement can be manually inducad, tne snucbers shall be inspected as follows: (a) At each refueling the maiti steam system (upstream of the main steam isolation valves) the main steam safety and power coerated relief valves and piping, auxiliary feecwater system, main steam supoly to the auxiliary feecwater pumo turbine, and letdown and charging portion of the CVCS system shall be inspected to determine if there has been a severe dynamic event. (b) In the event of a sever; dynamic event snuboers in that system wnich experienced the event shall be inspected during the refueling outage to assure that the snuceers have freedom of movement and are not frozen uo. The inspection shall consist of verifying freedcm of motion using one of the following: (i) Manually induced snubber movement; (ii) evaluation of in olace snucber piston setting; (iii) stroking the mechanical snuceer througn its full range of travel.
If one or more mecnanical snucbers are found to be frozen uc during this inspection, those snubbers shall be replaced (or overnauled) before returning to power. Re-inspection shall subsequently be performed according to the schedule of 4.7.8(a), but the scoce of the examination shall be limitec to the systems listed aoove. O Snubbers whien acoear inocerable as a result of visual inspections may be determined OPERABLE for the purpose of estaolishing the next visual inspection interval, providing that (1) the cause of the rejection is clearly estaolished and remedied for that particular snuceer and for other snucbers that may be generically susceptible; and (2) the affected snubber is functionally tested in the as found condition and detarmined OPERABLE per Specifications 4.7.8.d or 4.7.8.e, as applicable. Hydraulic snubbers which have uncovered fluid ports shall be tested by starting with the piston at the as found setting and extending the piston rod in tne tension mode direction. All snuobers connected to an inoperable common hydraulic s fluid reservoir shall be counted as inoperable snubbers. ..
- c. Functional Tests " # '" "##
At least once per 18 months during shutdown, representative s mole" of either (1) at least 10% of the totalCopreggh//pejof snubb .5 n use in the plant shall be functionally testec enaer in place or in a bench test. For each snuocer that does not meet the fuactional test acceptance criteria of Specification 4.7.8.d or 4.7.8.e, an KffFFy additional 10% of that type of snubcer shall be functionally tested until no more failures are found or until all snubbers have been j WEA functionally tested. pp .Sf M * }
"The requirements of this section for functionally testing mechanical snucbers O7 may be waivec until str rtup following the first refueling outage.
t McGUIRE - UNIT 1 3/4 7-2T lat:Y z- '/9
.--7 A PLANT SYSTEMS O
SURVEILLANCE REOUIREMENTS (Continued) or (2) A representative sample of each type of snubcer shall be functionally tasted in accorcanca with Figure 4.7.1, =hich includes accaptance and rejection critaria. On Figure 4.7.1, "C" I is the total number of snucbers found with Iccking veiccity l or bleed rate or drag force (if acclied) not .:eeting .he acceptanca requirements. by "N". The cumulative number of snucbers testad is denoted At the end of each oay's tasting, the new values of "N" and "C" (previous day's tota! ;1us current day's incrseerrts) shall ce plotted on Figure 4.7.1. If at any time the point plattad f alls in the " Reject" region all snuchers of that tjpe shall be functionally tested. If at any time the point plottad falls in the " Accept" region testing of that type of snuceer shall be ta ::inatad. When the acint plottad lies in the " Continue Testing" regica, additicnal snutoers shall be tastad until tne point falls in :ne "Accapt" ium r ragion or tne " Reject" region. or all the snWoers of : hat type arrm1mt-r\ o c, <>
> nave caen testac. r' @ zw; A rrecdm.su r '*8 )
The e2presentative sample selected for functional testing shall include the various configurations, operating environments and the 4 range of site and capacity of snuccers. The representative sample l1 X) shall be selected randomly from the total population;inntificc-
-in TeLia 2.7 'c :rd 3.7 db.
Snubbers identified ia Tables 2.c :nd 0.7-'b- as "Escecially Difficult to Remove d or in "Hign Radiation Zones Curing Shutccwn"
,m 4 ", r^ ' * '-
." ~"Jghal.1FT.Mj 'Myal o.be included in the representative sancie."
be used jointly or separately as the basis for 6 sampling plan. ,rutE gjsg. ' A rrA camtur r
- y. In addition to the regular samole, snubbers placed in the same location as snubbers which failed the previous functional test shall
! be ratested during the next tast period. Test resuits of these
/ r snuocers shall not be incluced in the sampling plan.
^ {,'* * '^. r
, kf any snubber selected for functional tasting either fails to a
lockup or fails to move, i.e. , frozen in place, the cause will be ' 6m ro nsao; evaluated and if caused by manufacturer or design deficiency all snuobers of tne same design suoject to the same defect snall be 3
/*MWOW4 runctionally tested) This tasting requirement snall be indeoendent Meta d'P/ of the requirements stated acove for snuceers not meeting the % n.L t usa n t T w in functional test acceptance criteria.
1 ffsansta ir y Permanent or other exemptions from functional testing for individual snubbers in these categories may be granted by the Commission only if a justifiaole basis for exemption is presented and/or snuober life destructive testing was i {., performed to qualify snubber operability for all design conditions at either the cocletion of their fabrication or at a suosequent date.
-McGUIRE - UNIT 1 3/4 7-X , o vs.z r ?-
_.,:- . _ m . ,.3 : I PLANT SYSTEMS C s . SURVEILLANCE REGUIREMENTS (Continued) For the snubber (s) found inoperable, an engineering evaluation shall be performed on the ccmoonents which are su: ported by the snubber (s). The purpose of this engineering evaluation snail be to determine if the components supported by tne snuboer(s) were acversely affected by the inoperability of the snutter(,) in order :: ensure that the supported ccmconent remains capacle of meeting the designed service.
- d. Hvdraulic Snubbers Functional Test Accactance Criteria The hydraulic snubber functional test shall verify that:
- 1. Activation (restraining ac'on) is acnieved witair. the specified range of velocity or acceleratien in to:n tensi:n :nc compression.
- 2. Snubber bleed, or release rate, wnero recuired, is within the scecified range in e:mcression or tensier.. ?:r scu::ers specifically requirec a not displaca uncer c:n:icuous Icad, the aoility of the snu::er to withstanc lead witacu.
displacement snall be serified. {'
) e. Mechanical Snubbers Functiona! Test Accec:ance Cri ar'a J
The mecnanical snubber functional test shali verify that: l
- 1. The force that initiates free movement of the sau::er rod in either tension or cor:ression is less : nan tne scecified
$54 E7 5 maximum drag force.1 OtNey_ fore ,all V. nave ncreifed more tnay130 pe# tent Ainc~e -Ae last/s rveilJhnce t > . M i
- 2. Activation (restraining ection) is acnieved witnin the specified range of veloci y or acceleratica in teth tension and comoression.
- 3. Snucber release rate, wrera required, is wi:nin tne specified range in compression or tension. For snu::ers s:,ecifically required not to displace uncer continuous load, tne eoility of
, the snuober to withstanc icad without cispiacement shall be l verified.
- f. Snubber Service Life Monitorinc A record of the service life of each snubber, -he date at which the designated service life commences and the installation anc main-tenance records on which the :esignated service life is based shall be maintained as required by 5,:ecification 5.10.2.
O l U i McGUIR3 - UNIT 1 3/4 7-Ef 4/ UNIT - e
.-...~.
r O PLANT SYSTEMS . SURVEILLANCE REOUIREMENTS (Continued) Concurrent with -the first inservica visual inspection and at least once per 18 months thereaftar, the installation and mainenance records for each snubber 44 a':f '- ' - ' ' ='- --" ' ' it - shall be reviewed to verify that the indicated servics li'e has not been exceeded or will not be exceeded by more than IC: prior to the next scheduled snubber service life review. If the indicated service life will be exceeded by more than 10% prior to the next scheduled snubber service life review, the snubber service life shall. be reevaluated or the snubber shall be replaced or reconditioned so as to extend its servico life beyond the data of the next scheduled service life review. s The results of the reevaluation may be used to justify a change to the service life of the snuboer. This reevaluation, replace. ment or reconditioning snall be indicated in the records. u O McGUIRE - UNIT 1 3/4 7,23' ~z :L. uWr7 - _ , , . . _ . _ _ . . - . . . ---- - - ~ - ' ' ~
.. ,. . a .. _ D ~ . . ,--.l------ ,- - - - - - - - - - -~ ~ ~~ '~ ' f TTAC&1" Y b [pr S df Any inoperable snubbers that are found between visual inspection intervals will not be counted against the next visual inspection, provided such snubbers are found during an inservice functional test or during normal operation and maintenance activities which are not centrived to preclude them from an imminent visual inspection; additionally, all such snubbers are require <1 to be functionall'/ tested during the next visual inspection after they are found. O hs... -m miwp--a w
- ... ~ ~
, ,. ~.
te -, / W 1.$dr s i J O 3 Testing equipment failure during a day's functional testing may invalidate that { day's testing and allow that' day's testing to resume anew at a later time, providing all snubbers tested with the failed equipment during the day of equip-i ment failure are retested. i 1 1 I' l l 1 i t 1 O . i i b l l 6 1 1
'
- r .
b 77/ACNMSNT gzy f w i or (3) an initial representative sample of 55 shall be functionally tested and for each snubber detemined to be inoperable as the result of testing, another sample of at least 1/2 the size of the initial sample shall be tested until the total number tested is equal to the initial sample si::e multiplied by the factor,1 + C/2, where C is the nu=ber of snubbers found to be inoperable. This plan may be plotted using an " accept" line which follows the equation N = 55(1 + C/2). Each snubber should be plotted as soon as it is tested. If the point plotted f alls on or below the " accept" line, testing of that group r.ay be discontinued. If the point plotted falls above the " accept" line, testing of that group must continue (unless all snubbers in that group have been tested.) l 1 1 t O I y i j I t L) - e
\\ 09
(([O M M h 1[4[ 4 F g i,y.!~ A .,,,J- s~ u si,d n
, , , , ,.4.
If n'.1. 2. 7
. . .2 2.- M are used jointly, the total number of snubbers in the representative sample must be selected from the combined total of snubbers listed in both tables and shall contain.a proportionate number of each type snubber which reflects the percent of each type snubber in the total j population.
! Either two of the three sample plans may be used separately for testing either type of snubbers-11:: lu ;.'.,le s 2. 7 '
- 2M ? . -'----./4, providing that the total number of snubbers listed in an individual table is included in the selection of the representative sample as required by the sample plan being used for that individual table.
4 i i i f 4 V
. _ . _ . _ . _ _ _ _ . _ . _ . _ . -._._-.-_,...____.___m._ . . _ _ . . . _ . . _ _ _ _ _ . _ _ _ _ _ . _ . _ _ . . . - = _ . . . . _
___7.__. __A7799e MmENr? E 7~
# ,, g ,-f l@
l !. Snubbers may be functionally tested and calibrated at less than full !. rated load, providing that the load applied to the snubber during-testing l or calibration can be correlated to operability parameters at full rated l 1 load. i i- ! h ! I
- t. l 1
i f
@ 1 i
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, f 1 V i l 3 ACCEPT 2 /
0 to 20 3e e 50 80 70 80 so too N O FIGURE 4.7.1 SAMPLING PLAN FOR 5UNBBER FUNCTIONAL TEST McGUIRE - UNIT 1
- 3/4 7-23p
~
O O O , TABLE 3.7-4a ; 17- SAFETY REtATED llYDRAULIC SNUBBERS
- U u.
HIGil RADIATION SNU68ER SYSTEM SNU88ER INSTALLED ACCESSIBLE OR ZONE ESPECIALLY DIFFICULT NO. ON, LOCATION AND ELEVATION INACCESSIBLE KN DURING SilUIDOWN** TO REMOVE (A or I) (Yes or No) (Yes or No) C
'l cr ch/d=l
- Snubbers m.'y be added/to safety related systems without prior License Amendment to Table 3.7-4a
, provhied that a revision to Table 3.7-4a is included with the next License Amendment request. .
** Modifications to this column due to changes in high radiation areas may be made without prior '
License Admeneent provided that a revision to Table 3.7-4a is included with the next License
- Amendment request.
l I
, wl o-*
(Je 4 o
IABIE 3.7-4b llF} SAFETY HELATED HECilANICAL SNUBUERSA a - IIIGN HADIA110H SNUBDER SYSTEM SNUBBER INSTAL. LED ( j ACCESSIBLE OR 10 tie ESPECIALLY DIFFICULT NO. ON, LOCATION AND ELEVATION INACESSIBl E MMDURI,1G SHUIDOWN** l TO REMOVE (A or I) s [ (Yes or No) (Yes or No) '
; I N \ ;
\
i
@N !
N. \ I ( N f , h /a fea/
- Snubbers may be addedjto safety related systems without prior License Amendment to Table 3.7-4b l 3
provided that a revision to Table 3.7-4b is included with the next <icense Amendment request. (
** <1_s. Modifications to this column due to changes in high radiation areas may be without prior Am._.nt ._ ,.d t,.a t a _ , s ion t. ,as , e 3. >.4, , . , nc , .d w , t,.
. ..e _ t
O (' . ; , ~ p: I 'l^ * : .. s.e .ggy gh NT SYSTEM 5
~. . . , * , . _; r;. ; ,^1-9 S.
.a . . ., $._ r 5 ,. .-
VEILLANCE REQUIREMENTS (Continued)
- c. .",- ..,u"n-s?,.-' . ' ^ 3 9v$ , , :.
7._,. ,.l l:,..:. s ..r y%., %fy ?,4 s- s
'O..* i .,4 ; .493 , .
- b. Stored sources not in use - Each seaiec source anc 'ission detector d ' . E .f[. s .. .["):ps .
shall be tested prior to use or transfer to another licensee unless f #, -K tested witnin the previcus six months. 5ealec sources anc 'ission T.T 'M4, +LJ .: eR .: F -l ,. 0 w e
. "..a.
detectors transferred without a certi'icate incica*.ing ;ne last tes* 'MW( W . /~ ~ '/ ' ,.* . ' date shall be tested pr'or to Seing placed 'nto use. "D' .' <.h 4 d-'., t i
.V :,~ rn I
S .' c. Startup sources and fission detectors
- acn sea,,ec startuo source pri.. ?
- % y. Y3'M:--
,$s.. e,- :-
I anc fission detector snali ce tested <ithin 31 cays criar to being
? ' 4 Q .5 i .
[ 6. p g. &.g 3 (, f subjected to core ' lux or installed in the core and following repair v.# , - or maintenance to tne source.
-? .'
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. . s- ,. .;. . y .4.-
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.J6. 3 Reports - A recort snail be precarec and sucmitted to the Commission Q- .ij.); c an annual :: asis if sealed source or ss on cetector 'eaKage tests reveal i
a .l.} 1.J }},h; . K;.'; O . . presence of greater than or ecual to 2.;05 microcur i es of -emovable - tamination. sj,,(*g f. r 'i,.v,W .
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PLANT SYSTEMS 3/4.7.11 FIRE SUPPRESSION SYSTEMS FIRE SUPPRESSION WATER SYSTEM LIMITING CONDITION FOR CPEPATION
/C
- 3. 7. M'.1 The fire suppression water system shall be GFERABLE with:
,v n a.sr a.J(Two)firesuppressionpumos,eachwithacapacityof(2500)gpm, with their discharge aligned to the fire suppression heacer, b'.{} Separyte wateQ supprties/eaEn wit.W'a'Ininimum cEn'tainet volume-of--
/ gallons,-and
.; t e ur~~
- b. An OPERABLE flow path capable of taking suction from tAe 4,eek.
-=d the t:nb and transferring the water through districution piping with OPERABLE sectionalizing control or isolation valves to the yard hydrant curb valves, the last valve ahead of the water ficw alarm device on each sprinkler or hose stancpipe, and the last valve aheed of the deluge valve on each daluge or spray system recuired to be OPERABLE per Specifications 3.7.11.2, 3.7.11.5 and 3.7.11.6.
APPLICABILITY: At all times. ACTION:
- a. With e,e pump and/or one water supply inoperable, restore the ir.cper-able equipment to OPERABLE status within 7 days or, in lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the plans and procedures to be used to restore the inoperable equipment to OPERABLE status or to provide an alternate backup pump or supply. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
- b. With the fire suppression water system otherwise inoperable:
- 1. Establish a backup fire suppression water system withir. 24 hours, and
- 2. In lieu of any other report required by Specification 6.9.1, submit a Special Report in accordance with Specification 6.9.2:
a) By telephone within 24 hours, b) Confirmed by telegraph, mailgram or facsimile transmission O no later than the first working day following the event, and
, .25 i W-STS 3/4 7- X .ti:6 MAY I 51980 mi..-me....i i is ..iii. ..i.,. ..d
~
PLANT SYSTEMS ACTION: (Continued) c) In writing within 14 days following the event, outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERA 8LE status. I SURVEILLANCE RECUIREMENTS
/C l 4.7.M.1.1 The fire suppression water system shall be demonstrated CPERABLE:
8% ) Y
- h b h Y bY WW W th~e j W h a%*$~ f*L
- b. At least once per 31 days on a STAGGERED TEST SASIS by starting each electric motor driven pump and operating it for at least 15 minutes on recirculation flow.
- c. At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path is in its correct position.
- d. (At least once per 6 rrenths by performance of a system flush.4 c! ' 's cu >, . i. & >;,.,t/es 4 c,, ;- wn t y ne fic.. l !; < A -i; - .
- e. At least once per 12 months by cycling each tastacle valve in the flow path through at least one complete cycle of full travel.
- f. At least once per 18 months by performing a system functional test which includes simulatad automatic actuatica of the system througnout its operating sequence, and:
- 1. Verifying that each at,tematic valve in the flow path actuates to its correct position,
- 2. Verifying that each pump develops at least (2500) gpm at a fut-system frus.we huf :f "q) e 14 y'psay y
- 3. Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel, and
! 4. Verifying that each fire suppression pump starts (sequentially) l to maintain the fire suppression water system pressure greater
. than or equal to /2f psig,
- g. At least once per 3 years by performing a flow test of the system in accordance with Chapter 5, Section 11 of the Fire Protection Handbook, 14th Edition, published by the National Fire Protection Association.
9
,2. 7 M-STS 3/4 7.3( 4:*- '
MAY 15 ICSO l l l . . - - l
~
O \ PLANT SYSTEMS /
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SURVEILLANCE REQUIREMENTS (Continued) -
'Ns 4.7.11.1.2 NThe fire pump diesel engine shall be demonstrated OPERABLE:
/
N
- a. At le'ast once per 31 days by verifying:
- 1. The fuel storage tank contains at least gallons of fuel, and /
- 2. The diesel \ starts from ambient conditf'ons and operates for at least 30 min'utes on recirculation f, low.
'\ /
- b. At least once per 92 ' days by verifying that a sample of diesel fuel from the fuel storage tank, obtained'in accordance with ASTM-0270-65, is within the acceptable' limits specified in Table 1 of ASTM 0975-74 wnen checked for viscosity,'swater and sediment.
- c. At least once per 18 months, d6 ring shutdown, by subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's rec 6mmendations for the class of service.'
/ ,
4.7.11.1.3 The fire pump diesel sdarting 24-vol attery bank and charger shallbedemonstratedOPERABLE:/ g
- a. At least once per 7 ays by verifying that
- 1. Theelectrol,ytelevelofeachbatteryisahvetheplates,and 2.
/ \
The ove T1 battery voltage is greater than or equal to 24 volts.
- b. At least or)ce per 92 days by verifying that the specific gravity is appropriaYe for continued service of the battery.
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- c. Atleas! t once per 18 months by verifying that: \
- 1. The batteries, cell plates and battery racks show no visual indication of physical damage or abnomal deterioration,\ and
- 2. The battery-to-battery and tarainal connections are clean, tight, free of corrosion and coated with anti-corrosion mate, rial.
Q f- a,pp b *cr //x O W-STS /3(4g(3( MAY 15 7080 _ . ___________-______-_-_____-____________m__
l PLANT SYSTEMS SPRAY AND/OR SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION
,_ .: ./ ,, m : ~ ?.7-5 3.7.)4.2 The f !' :'9; spray and/or sprinkler systems {shall j be OPERABLE >
3.' y ant Tegenden Attfe3pmemncQ1 cga?.4cIf.-)-
$a' c.
ic l APPLICABILITY: Whenever equipment protected by the spray / sprinkler system is required to ce OPERABLE. ACTION:
- a. With one or more of the above required spray anc/or sprinkler systems inoperable, within one hour establish a continuous fire waten with backup fire suppression equipment for those areas in wnich redundant systems or components could be damaged; for other areas, establish a hourly fire watch patrol. Restore the system to OPERABLE status within 14 days or, in lieu of any other report required by Specifica-tion 6.9.1, crepare and sucmit a Special Report to the Ccmmission pursuant to Specification 6.9.2 within the next 30 days cutlining the action taken, the cause of the inocerability and tne plans and schedule for restoring the system to OPERABLE status.
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicaole.
SURVEILLANCE REOUIREMENTS If i 4. 7. )T. 2 Each of the above required spray and/or sprinkler systems shall be ! demonstrated OPERABLE:
- a. At least once per 31 days by verifying that each valve (manual, power operated, or automatic) in the flow path is in its correct position.
l
- b. At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel.
l l I O l W-STS 3/4 7-X
- NOV 2 01?c0
- r. . . _ . . . _ _ _ _ _ _ _ -. _ . _ . _ . . _ _ . . _. _ . - _ . _ . .- . . . .
/s C PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- c. At least once per 18 months:
- 1. By performing a system functional test whicn includes simulated automatic actuation of the system, and:
r e o ir onre c_tesf , s , a Arf dycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel.
- 2. By a visual inspection of the dry pipe spray and sprinkler headers to verify their integrity, and
- 3. By a visual inspection of each nozzle's spray area to verify the spray pattern is not obstructed.
('g d. At least once per 3 years by performing an air flow test through V > sach open head spray / sprinkler header and verifying each open head spray /sprinkitr nozzle is unobstructed. l l 1 0 y-STS 3/4 7- W * - U NOV 2 01330
-- - . - , . . - - , - - _ , , , . . , y _ -,p .-. , - , _ _ ,.s -
1 hfG f/ CO $ LANT SYSTEMS g2, SYSTEMS I LIMITING CONDITION FOR OPERATION / N. s 3.7.11.3 The following high pressure and low pressure CO
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systems jhall be OPERA 8LE. N 2 a. N (Plantgdepencent - to be listed by name and locatioru)
/
- b. \ !
- c. 'x r j
/ -
APPLICABILITY: Wheneve'r s equipment protected by the CO / systems is required to be CPERABLE. ' 2
/
/
ACT!CN: s /
- a. With one or more of h.he above required'CO, systems inoperaole, witnin one hour estabitsh a continuous fire watch witn backuo fire suppression equipment for those ar,e'a3 in which redundant systems or components could be damag'ed; for dther areas, establish an hourly fire watch patrol.
days or, in lieu of Restore any other \the r/s'ystem to CPERA8LE status within 14 eport required by Specification 6.9.1,prepareandsubmita%ecialReporttotheCommissionpursuant to Specification 6.9.2 with'n the next 30 days outlining tne action takan, the cause of the i perabKlity and the plans and schedule for restoring the system to ERABLE status.
\
- b. The provisfors of Spe fications 3.b'h3 and 3.0.4 are not applicable.
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St>RVEILLA_NC.E REGUIREMENTS ,
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4.7.11.3.1 Each o' the ove required Co., systems s.all be demonstrated OPERABLE at least once r 31 days by verifying that each valve (manual, power operated or automatic) in the flow path is in its correct position. 4.7.11.3.2 Each o \ l he above required low pressure CO 2 systems shall be demonstrated OPERA E:
- a. At lea once per 7 days by verifyirg the CO,, storage tank level to be gr ater than and pressure to be greater thar( psig, and j
- b. At east once per 18 months by verifying: \
\
l The system valves and associated ventilation damper's and fire door release mechanisms actuate manually and automatically, i upon receipt of a simulated actuation signal, and l
- 2. Flow from each nonle during a " Puff Test.*
l l W _-STS V,$/Q34 , MAY 15 icSO l l
l O) t TABLE 3.7-5 SPRAY AND/OR SPRINKLER SYSTEMS
- a. Elevation 695 ft. - Auxiliary Building Room No. Eouipment 501 RHR Pump 1A 500 RHR Pump 18
- b. Elevation 716 ft. - Auxiliary Building Room No. Eauicment 600 Aux. FW Pump Room - l> nit 1 649 Nuclear Services Water Pumps 627 Centrifugal Charging Pumo iA 630 Centrifugal Charging Pump 1B
- c. Elevation 733 f t. - Auxiliary Building Room flo. Ecuioment 723 Cemponent Cooling Pumps 701 Sattery Room Trench Area l d. Elevation 750 ft. - Auxiliary Buildir:g i
Room No. Eculprnent 801 Cable P. con - Unit 1
- e. Elevation 725 ft. - Reactor Building
- 1) Pipe Corrider
- f. Elevation 738 ft. - Reactor Building
- 1) Annulus -
.- t
[ lo ? r .
.l t .
V McGUIRE - UNIT 1 3/4 7-)& - JUN 1931
f 4 / f /E:~'1. Ui o PLANT SYSTEMS SUR NCE REQUIREMENTS (Continued) 4.7.11.3.3 x - EachofstheaboverequiredhighpressureCQ(s'ystemsshallbe demonstrated OPERABL
- a. At least once pe n5 months by verf ing the CO2 storage tank weight to De at least 90% full ch ~e weight.
- b. At least once per 18 mo by:
- 1. Verifying th systam, includla fire door lease mechanisms,atg ates associated manuallyventilation dampers and and automatically, upon r afpt of a simulated actuati 1, and
- 2. rformance of a flow test through headers nozzles to assure no blockage.
,/ '
a O - O PSTS 3'/fyf35' ' 5M i l
PLANT SYSTEMS HALON SYSTEMS LIMITING CCNDITION FOR OPERATION j
'~.3
- 3. 7.14'. A The following Halon systems shall be OPERABLE.
- a. (Plant dependent - to be, listed by name and location.)
c, f".~ . c. In > <. 8 c. APDLICABILITY: Whenever equipment protected by the Halon system is required to De OPERABLE. l ACTION:
- a. With one or more of the above required Halon systems inocerable, within 1 hour establisn a continuous fire waten with backup fire suceression equipment for those areas in which redundant systems or components could be damaged; for other areas, establish an hourly fire wctch patrol. Restore the system to CPERABLE status A hin 14 days or, in If eu of any other report required by Specifica-tion 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the sc:icn taken, the 25.use of.the inoperability and the plans ard schedale for restoring T.he system to OPERABLE status.
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE RE00!REMENTS
/S. 3 4.7 7 7 Each of the above required Halon systems shall be demonstrated OPERABLE:
- a. At least once per 31 days by verifying that each valve (manual, power operated, or automatic) in the flow path is in its correct position.
- b. At least once per 6 months by verifying Halon storage tank weight to be at least 95% of full charge weight (or level) and pressure to be at least 90% of full charge pressure.
l
- c. At least once per 18 months by:
1., Verifying the system, including associated ventilation dampers and fire door release mechanisms, actuates manually and auto-matically, upon receipt of a simulated actuation signal, and
- 2. Performance of a flow test through headers and nozzles to assure no blockage.
1 W-STS 3/4 7-JF s/ f .NOV 2 0150
P $X$ S LIF 10
,$FOROPEkSION
, / /
y'p/ 3.'7.1 - llfo o 'ng s. s 1 e - LE '
/ st havi g a
~
eas % c e we' 3_. 0*. ' ' lb roe p sure, - - - . f a. Elevation 716 f t. - Auxiliary Building
?
/ Room No. Eauipment la' 500 8 Turbine Driven Aux. FW Pump - Unit 1
-~
- b. Elevation 733 ft. - Auxiliary Building Room No. Ecuioment 703-704 Diesel Generators - Unit 1
' APPT2ICi pycE' Q --
'. AviEnev
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WMs ' IGNw p
- a. ,it on -
a
- utrec Ha s' .. n ,,
atch 'i.. bacM . j're w ' J O.* r . +a a aj iuo j' s
. ef se ay n which . t sys+/ or 1 -
gedi f y ara ,'estab b ,our a . estoe ,f9st(m L atus Sithi ' ays i, of otti , de . re - ed pec'# ppursu
- 6. 9A,/p' tep a submi ',4' ci 1 ort a +
t if 6.9. in t . ext ' ay # inino " v1 a n, ause o' e inoper i and-th la _ ule for r toring es to OP .s v
.b. T 1 t'on .0.3 r . are not app 1' le.
l' 1' EQlR 75 . _ l 4 of t o e d iystem s'
/ ,
- a. .I o ra'to or'auta-t er 3 ays y fyin flo gath is 'in
, at/each a}y s4 nu ' l er siti ic)/. ,
V y- / 7- M 3 2-McGUIRE UNIT 1 7-19' 1981 vaf7 z JUN
}
E { e O PLANT SYSTEMS FIRE HOSE STATIONS LIMITING CONDITION FOR OPERATION
/C. h' G i
3.7. M t$' The fire hose stations shown in Table 3.7-J shall be OPERABLE. APPLICABILITY: Whenever equipment in the areas protected by the fire hose stations is required to be OPERABLE. ACTION:
- a. With one or more of the fire hose stations shown in Table 3.7-X inoperable, route an additional equivalent capacity fire hose to the unprotected area (s) from an OPERABLE hose station within I hour if the inoperable fire hose is the primary means of fire suppression; otherwise, route the additional hose within 24 hours. Restore the fire hose station to OPERABLE status within 14 days or, in lieu of any other report required by Specification 6.9.1, prepare and sub=it a Special Report to the. Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability, and plans and schedule for restoring the station to OPERABLE status.
- b. The previsions of Specifications 3.0.3 and 3.0.4 are not acplicable.
8 SURVEILLANCE REOUIREMENTS
~~
l /c. y 4.7.R.S Each of the fire hose stations shown in Table 3.7-I shall be l demonstrated OPERABLE:
- a. At least once per 31 days by a visual inspection of the fire hose stations accessible during plant operations to assure all required equipment is at the station.
- b. At least once per 18 months by:
- 1. Visual inspection of the stations not accessible during plant operations to assure all required equipment is at the station,
- 2. Removing the hose for inspection and re-racking, and
- 3. Inspecting all gaskets and replacing any degraded gaskets in the couplings.
- c. At least once per 3 years by:
- 1. Partially opening each hose station valve to verify valve OPERABILITY and no flow blockage.
- 2. Conducting a hose hydrostatic test at a pressure of 150 psig or at least 50 psig above maximum fire main operating pressure, whichever is greater.
O W-STS 3/4 7-W # 13 l
'NOV 2 19R1 1
'r~- - -__ $
G
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TABLE W FIRE HOSE STATIONS LOCATION" ELEVATION HOSE RACK #
^ ,
!- ygi? .
/ j.1 g g / /
,g. e- -
O l
" List all Fire Hose stations required to ensure the OPERABILITY of safety-related equipment.
O i rsTs k f g36 . soy 2 a :na
O' TABLE 3.7-6 FIRE HOSE STATIONS e LOCATION ELEVATION 55-FF 695 ft. 52-CC 716 ft. 5*-CG 716 ft. 55-M:A 716 ft. 51-MM 716 ft. 40-AA 733 ft. 40-CC 733 ft. 43-00 733 ft. 46-AA 733 ft. 52-00 733 ft. 52-EE 733 ft. 54-GG 733 ft. 51-JJ 733 ft. 52-MM 733 ft. 55-NN 733 ft. 46-CC 750 ft. 51-CC}}