ML20206A378
| ML20206A378 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 11/09/1988 |
| From: | SYSTEM ENERGY RESOURCES, INC. |
| To: | |
| Shared Package | |
| ML20206A355 | List: |
| References | |
| GL-87-09, GL-87-9, NUDOCS 8811150099 | |
| Download: ML20206A378 (70) | |
Text
{{#Wiki_filter:_ _ _ _ _ _ _ _ _ _ . Plot t NL 88 01 , v( . 3/4.0 AFPLICABILITY LIMITING CONDITION FOR OPERATION 3.0.1 Compliance with the Limiting Conditions for Operation contained in the succeeding Specifications is required during the OPERATIONAL CONDITIONS or other conditions specified therein; except that upon failure to meet the Limiting Conditicns for Operation, the associated ACTION requirements shall be met. 3.0.2 Noncompliance with a Specification shall exist when the 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, completion 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 an OPERATIONAL CONDITION in which the Specification does not apply by placing it, as applicable, in:
- 1. At least STARTUP within the next 6 hours,
- 2. At least HOT SHUTD0hH within the following 6 hours, and
- 3. At least COLD SHUTD0hw 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 specified time \ limits as measured from the time of failure to scet the limiting Condition for Operation. Exceptions to these requirements are stated in the individual Speci- ,
fications. This specification is not applicable in OPERATIONAL CONDITION 4 or 5.
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Piol NL 88-of ! l l APPLICA8ILITY l SURVEILLANCE REQUIREMENTS ' 1 F 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS i or other conditions specified for individual Lir.iting 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 l
- b. The combined time interval for any 3 consecutive surveillance intervals shall not exceed 3.25 times the specified surveillance interval.
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i 4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicable condition shc11 not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the _ _ applicable surveillance interval or as otherwise specified. 4 [!NSElTlC) l 4.0.5 Surveillance Requirements for inservice inspection and testing of ASME l Code Class 1, 2, 8, 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 1. pumps and valve; 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),
- b. Survet11ance intervals specified in Section XI of the ASME Soiler ,
and Pressure Vessel Code and applictble I,ddenda for the inservice inspection and testing activities required by the ASME Soiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications: ASME Boiler and Pressure Vessel Required frequencies ) Code and applicable Addenda for parforming inservice - terminology for inservice inspection and testing inspection and testino activities activities Weekly At least once per 7 days t Monthly 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 276 days ' Yearly or annually At least once per 366 days l GRAND GULFS 1 3/4 0-2 Amr w r %. _ ;
% st-on Pio4 INSERT A i 3.0.4 Entry into an OPERATIONAL CONDITION or other specified condition shall t
not be made when the conditions for the Limiting Conditions for Operation are gt met and the associated ACTION reouires a shutdown if they are not ret within a sDecified time interval. Entry "nto an OPEPATIONAL CON )lTION or specified condition may be made in accordance with ACTION requirements when { conromance to them permits continued operation of the facility for an f unlimited period of timr. This provision shall not prevent passage through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual specifications. INSERT B I j 4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Specification 4.0.2. shall constitute l noncompliance with the OPERABILITY recuirements for a Limiting Condition for Operation. The time limits of the ACTION reouirements are applicable at the i time it is identified that a Surveillance ReQuirerent has not been perforced. The ACTION requirements may be delayed for up to 24 hours to permit the , comDletion of the surveillance when the allowable outace time limits of the
- ACTION recuirerents are less than 2A hours. Surveillance Requirements do not have to be perfomed on inoperable equipment.
a . INSERT C This provision shall not prevent passage through or to OPERATIONAL CONDITIONS as required to corrply with ACTION requirerents. l l l l l l J16 MISC 88080201 - 2
Pior NL Bb Cl REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERAT!EN (Continued)
~ '
, ACTION (Continued) i 2. If the inoperable control rod (s) is inserted, within one hour disars the associated directional control valves" either:
a) Electrically, or b) H.craulically by closing the drive water and exhaust water isolation valves. Otherwise, be in at least HOT SHtrTDOW within the next 12 hours.
- :. L y,v,;.; n. ef '+ecificetien 3.0.4 ore m eppliceMe--
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- c. With more than 8 control rods inoperable, be in at least HOT SHUTDOW within 12 hours.
d. With one scram discharge volute vent valve and/or one scram dischargs volse drain valve inoperable and open, restore the inoperable valve (s) to theCPERABLE status within 24 hours or be in at least HOT SMtfTDOW withia next 12 hours,
- e. With two scram discharge voluee vent valves and/or two scram discharge volume drain valves inoperaele and open, restore one valve in the vent line and one valve in the drain line to OPERABLE status within 8 hours and restore all valves to OPERABLE status within the next 16 hours or c1cie at least SHUTDOW onethe within vent valve next and one drain valve and be in a least HOT 12 hours, f.
With any scram discharge volume vent valve (s) and/or any scras discharge volume drain valve (s) inoperable and closed except when required by ACTION statement e. above, restore all valves to CPERABLE status within , 8 hours or be in at least HOT SHUTDOW within the next 12 hours. SURVE!LtAN t Rf0VIIEMENTS 4.1.3.1.1 The scram discharge volurie drain and vent valves shall be der.cnstrated OPERABLE by: i a. At least once per 31 days verifyinC each valve to be open,* and
- b. At least once per 92 days cycling each valve through at least one l complete cycle of full travel.
l l "These valves may be closed intermittently for testing under administrative ! controls.
**May be rearted intereittently, under administrative control, to permit testing associated with restoring the control rod to OPERABLE status.
GRAND GULF UNIT 1 3/4 1-4 - Amendsent No. 21.-
-5444u M M ta:
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REACTIVITY CONTROL SYSTEMS k, LIMITING CONDITION FOR OPERATION (Continued) A,CTION: (Continued)
- b. With a "slow" control rod (s) not satisfying ACTION a.1, above:
- 1. Declare the "slow" control rod (s) inoperable, and
- 2. Perform the Surveillance Requirements of Specification 4.1.3.2.c at least once per 60 days when operation is continued with three or more "slow" control rods declared inoperable.
Otherwise, be in at least HOT SHUTDOWN within 12 hours,
- c. With the maximum scram insertion time of one or more control rods exceed-ing the maximum scram insertion time limits of Specification 3.1.3.2 as determined by Specification 4.1.3.2.c, operation may continue provided that:
- 1. "Slow" control rods, i.e., those which exceed the limits of Specifi-cation 3.1.3.2, do not make up more than 20% of the 10% sample of con-trol rods tested.
- 2. Each of these "slow" control rods satisfies the limits of ACTION a.1,
- 3. The eight adjacent control rods surrounding each "slow" control rod are:
a) Demonstrated through measurement within 12 hours to satisfy the maximum scram insertion time limits of Specification 3.1.3.2, and b) OPERABLE. ( 4. The total number of "slow" control rods, as determined by Specifica-tion 4.1.3.2.c, when added to the sum of ACTION a.3, as determined by Specification 4.1.3.2.a and b, does not exceed 7. Otherwise, be in at least HOT SHUTDOWN within 12 hours,
- d. Th: pr:vi:br.: f 5;::!'ic:ti:r 3.0.' cr: ret :;;1f: 210.
SURVEILLANCE REQUIREMENTS 4.1.3.2 The maximum insertion time of the control rods shall be demonstrated through measurement with reactor coolant pressure greater than or equal to 950 psig and, during single control rod scram time tests, the control rod drive pumps isolated from the accumulators:
- a. For all control rods prior to THERMAL POWER exceeding 40% of RATED THERKAL POWER following CORE ALTERATIONS
- or af ter a reactor shutdown that is greater than 120 days,
- b. For specifically affected individual control rods ** following rainten-ance on or modification to the control rod or control rod drive system which could affect the scram insertion time of those specific control rods, and
- c. For at least 10% of the control rods, on a rotating basis, at least once per 120 days of POWER OPERATION.
' Except normal control red movement.
(;' **The provisions of Specification 4.0.4 are not appli able for entry into OPERATIONAL CONDITION 2 provided this surveillance is completed prior to entry into OPERATIONAL CONDITION 1. GRAND GULF-UNIT 1 3/4 1-7 Amendment No.35. -
Plo1 NL4t01 REACTIVITY CONTROL SYSTEMS CONTROL R00 SCRAM ACCUMULATORS LIMITING CONDITION FOR OPERATION 3.1.3.3 All control rod scram accumulators shall be OPERABLE: APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 58 ACTION:
- a. In CPERATIONAL CONDITIONS 1 and 2:
- 1. With one control red scram accumulator inoperable, within 8 hours:
a) Restore the inoperable accumulator to OPER BLE status, or b) Declare the control rod associated with the inoperable accumulator inoperable. Otherwise, be in at least HOT SHUT 00WN within the next 12 hours.
' With more than one control rod scram accumulator inoperable, 2.
declere the associated control rods inoperable and a) If the control rod associated with any inoperable scram accumulator is withdrawn, immediately verify that at least one control red drive pump is operating by inserting at least one withdrawn control rod at least one notch or place the reactor mode switch in the Shutdown position. b) In6ert the inoperable control rods and disars the associated directional control valves either:
- 1) Electrically, or
- 2) Hydraulically by closing the drive water and exhaust water isolation valves. ;
Otherwise, be in at least HOT SHUTDOWN within 12 hours. y 3
- b. In OPERATIONAL CONDI110N 5*:
- 1. With one withdrawn control rod with its associated scram accumulator inoperable, insert the affected control rod and K disare the associated directional control valves within one j ,
hour, either: a) Electrically, or f, b) Hydraulically by closing the drive water and exhaust water j isolation valves.
- 2. With more than one withdrawn control rod with the associated ,
t - scram accumulator inoperable or with no control rod drive pump ' operating, issediately place the react'r mode _switcNin the_ _ {t; 3C'!M: ~: tr y - Shutdown position. , c: r.:t :;;9f 9?:f
- c. N prev 5f ri ef !;;:!'!:stf - L O.'
i INSERT t least tne accumulator associated with each withdrawn control rod. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2. -
- -. - . - . - - - -. - . . - , - .,c . -- , -
P ioB NLtt-et f 8 INSERT r
- 5 hc.
V With one or more accumulator pressure detector or alarm inoperable, verify accumulator pressure to be 11520 psig at laast once per 24 hours, e or declare the associated accumulator inoperable, 6 With one or more accumulator leak detector or alare inoperable, verify Od 4, accumulated water drained at least sne per 48 hours, or declare the associated accumulator inoperable. ', h I l l J14MISCS80707 - 1 I
ML 68.cl p gq REACT!v!TY CONTROL SYSTEMS CONTROL R00 DRIVE COUPLING LIMITING CONDITION FOR OPERATION 3.1.3.4 All control rods shell be coupled to their drive mechanisms. APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 5*. ACTION:
- a. In OPERATIONAL CONDITION 1 and 2 with one contrcl rod not coupled to its ,*
associated drive mechanism, within 2 hours: ,
- 1. If permitted by the RPCS, insert the control rod drive mechanism to '
accomplish recoupling and verify recoupling by withdrawing the control rod, and: a) Observing any indicated respoast of the nuclear instrumentation, , and
, b) Demonstrating that the control rod will not go to the overtravel position.
- 2. If recoupling is not accomplished on the f,irst attempt or, if not permitted by the #PCS, then until permitted by the RPC5, declare the control rod inoperaDie, insert the control rod, and disarm the associated directional control valves ** either:
a) Electrically, or b) Hydraulically by closing the drive water and exhaust water isolation valves. Otherwise, be in at least HOT SHUT 00VN within the next 12 hours, i
- b. In OPERATIONAL CONDITION 5' with a withdrawn control rod not coupled to its associated drive sechanism, within 2 hours either: ;
l
- 1. Insert the control rod to accomplish recoupling and verify recoupilng by withdrawing the control rod and demonstrating that the control rod will not go to the overtravel position, or
- 2. If recoupling is not accompliche d insert the control rod and disarm the associated directional control valves ** either: j 1
a) Electrically, or b) Hydraulically by closing the drive water and exhaust water isolation valves.
-c. %: pr:.i;!:n; cf !;;:!'!::tt:n 3.0 ' : : net ::"We- ,
l a i At least each withdrawn control rod. Not applicable to control
- rods removed ;
per Specification 3.9.10.1 or 3.9.10.2. , May be reareed intermittently, under adsinistrative control, to permit testing ; associated with restoring the contr'1orod to OPERABLE status. 3/4 1-10 GRAND CULF UNIT 1 bKl>WCWT No. _
b II0 ML 68 0% REACT!v1TY CONTROL SYSTEMS CONTROL R00 P0$1T10N IN0! CATION LIMITING CON 01 TION FOR OPERATION 3.1.3.5 At lea'st one control rod position indication systes shall be OPERA 8LE. APPLICA4!LITY: OPERATIONAL CON 0!TIONS 1, 2, and 5". ACTION:
- a. In OPERATIONAL CON 0! TION 1 or 2 with one "
or more control rod position indicators inoperable, within one hour:
- 1. -Determine the position of the control rod by the alternate control rod position indicator, or
- 2. Move the control rod to a position with an OPERABLE position indicator, or
'3. When THERKAL POWER is:
a) Within the low power setpoint of the RPCS:
- 1) Declare the control rod inoperable, and
- 2) Verify the position and bypassing of control rods with inoperable "Full-in" and/or "Full-out" position indicators by a second licensed operator or other technically qualified members of the unit technical staff, b) Greater than the low power setpoint of the RPCS, declare the control rod ff. operable, insert the control rod, and diaara the associated directional control valves ** either:
- 1) Electrically, or
- 2) H draulically by closing the drive water and exhaust water i olation valves.
Othenvise, be in at least HOT SHUTOOWN within the next 12 hours.
- b. In OPERATIONAL CON 0! TION 5" with both control rod position indicators for
- a withdrawn control rod inoperable, move the control rod to a position with an OPERABLE perition indicator or insert the control rod.
- 0. % ;r:;hh : c' !;::t' h:t hr. 3.0,t ;r; = t ;;' k d';.
"At least each withdrawn control rod. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
""May be rearsed intermittently, under administrative control, to permit testing associated with restoring the control rod to CPERABLE status.
GRAND GULF UNIT 1 3/4 1-12 Amtervt 4.
NL M-ci , Pill IN31euwfNTA? ION - TABLE 3.3.3 1 (Continued) EMERGEN0Y CORT C001,1N3 5YSTEM ACTUATION INSTRLMENTATION
~~ '
ACTION A:T!0h 30 - With the number of OPERABLE channels less than reau' i by the Minimum CPERA8tt Channels per Trip Function requiret. ::
- a. With one channel inoperable, place the i pera:le channel in the tripped condition within one hour or seclare the associatec systee(s) inestrable,
- b. S'ith Fore than ont channel inoperable, declare the associatec sys.em(S) inonerela.
A: TION 31 - With the number of OPERA!LE channels less than reoviree by the Minier OPERA 8LE Channels per **1p Function roovireeent. ce:lare the asse:iatee ADS tt : sytter or ECCS inoperable. A:T10h 32 With the nu.ter of OPERA!LE channels less than requirac by the Minimue OPERABLE Channels per Trip Function requirement, restore the inoperatie channel to OPERA 8LE status witnin a hours
. or oe:lare the associatec ADS trir system er ECC5 inoperable.
A; TION 53-i With the nummer of OPERABLE channels less than recuired by the Minisse OPERABLE Channels per Trip Function requirement, p*a:e the inoperatie channel (s) in the tripped concition within ent hour or ce:lare the HPCS syster inoperable. A:T!0h 38 - With the nua.se of OPERABLE channel less than reovired by the i Minine C* IRA 5LE Channels per Trip Fsnction reautrecent, pla:e - at least one l'soerable channel in the tripped condition within
; onehour\oresclaretheHP5 system ineperable.
i A:T!cs 35 - With the number of OPERAILE channels less than reavited by the Minieve OPERAI.! Channels per Trip Function requirement, place
' the sinoperable channel (s) in the tripped condition within one
, hou?\orceclaretheassociatedsystee(s)insperable.
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- 1. *
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'U TABLE 3.3.6-1 ,
es a CONTROL 200 BLOCK INSTRUDENTATION y O MINIptM APPLICABLE o OPERATIONAL 9 OPERA 8tE CHANNELS
. CONDITIONS _ ACTION TRIP FUNCTION PER TRIP FUNCTION 0 1. R00 PATTERN CONTNOL SYSTEM 2 1, 2 60
- a. Low Power Setpoint 1, 2 60 High Power Setpoint 2 b.
- 2. APRM
- a. Flow Blased Meutron Flux- 6 1 61 Upscale 1, 2, 5 61 Inoperative 6 ,
- b. 6 1 El
- c. Downscale 6 2, 5 61
- d. Neutron Flux - Upscale, Startup R 3. SOURCE RANGE MONITORS 4 2 61
- a. Detector not full in( 2** 5 62 4 2 61
- b. Upscale (b) 5 62 2**
4 2 61
.: . Inoperative (b) 5 62
/ 2** 2 61 IC) 4
- d. Downscale 2** 5 62 1 , ,
- a. INTERMEDIATE RANGE MONITORS 61 6 2, 5 fgh a. Detector not full in 6 2, 5 61
- b. Upscale 2, 5 61 6
d c. Inoperatig) i l [j y t - < i
- d. Downscale 6 2, 5 61 I j 5. SCRAM DISCHANGE VOLUPE
- a. Water Level-High 2 1, 2, 5* 62 93
- 6. REACTOR C00UWT SYSTEM RECIRCULATION FLOW 3 1 62
- a. Upscale 3, 4 63 2
- 7. REACTOR MODE SWITCH SHUT 00WN POSITION
PtB A $$ O\ INSTRUMENTATION TABLE 3.3.6-1 (Continued) CONTROL ROD BLOCK INSTRUMENTATION ACTION ACTION 60 - Declare the RPCS inoperable and take the ACTION required by Specification 3.1.4.2. ACTION 61 - With the number of OPERABLE Channels:
- a. One less than required by the Minimum OPERABLE Channels per Trip Function requirement, restore the inoperable channel tc OPERABLE status within 7 days or place the inoperable channel in the tripped condition within the ne.tt hour. .
- b. Two or more less than required by the Minimum OPERABLE
' Channels per Trip Function requirement, place at least one inoperable channel in the tripped condition within one hour. ACTION 62 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, place the inoperable channel in the tripped condition within of.4 hour. ACTION 63 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, initiate a rod block. NOTES
- With more than one control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2
"" OPERABLE channels must be associated with SRMs required OPERABLE per Specification 3.9.2.
(a) This function shall be automatically bypassed if detector count rate is
> 100 cps or the IRM channtis are on range 3 or higher. l (b) This function shall be automatically bypassed when the associated IRM channels are on range 8 or higher.
(c) This function shall be automatically bypassed when the IRM channels are on range 3 or higher. (d) This function shall be automatically bypassed when the IRM channels are on range 1..
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L*3AT:0N". C50!!!S 5. _ _ GRAND GULF-UNIT 1 3/4 3-54 h ev m -4 N . - l
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]NSTRUMENTATION 3/4.3.7 MONITORING INSTRUMENTATICN RADIATION MONITORING INSTRUMENTATION L1h! TING CONDITION FOR OPERATION 3.3.7.1 The radiation monitoring instrumentation channels shown in Table 3.3.7.1 1 shall be OPERABLE with their alarm / trip setpoints within the specified limits.
APPLICA81LITY: As shown in Table 3.3.7.1-1. ACTION:
- a. With a radiation monitoring instrumentation channel alare/ trip setpoint exceeding the value shown in Table 3.3.7.1-1, adjust the
- setpoint to within the limit within 4 hours or declare the channel inoperable,
- b. With one or more radiation monitoring channels inoperable, take the ACTION required by Table 3.3.7.1-1.
- c. The provisions of Specificationf 3.0.3 rd LO.' are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.7.1 Each of the above required radiation monitoring instrumentation channels shall be demonstrated OPERABLE by the perforsance of the CNANNEL CNECK, CNANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the conditions and at the frequencies shown in Table 4.3.7.1-1. GRAND GULF-UNIT 1 3/4 3-58 bra x,4 W
NL SS-On Plis INSTRUMENTATION S SEISMIC MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERAT10N 3.3.7.2 The seismic monitoring instrumentation shown in Table 3.3.7.21 shall be OPERABLE.
- APPLICABILITY: At all times.
ACTION:
- a. With one or more of the above requirad seismic monitoring instruments inoperable for e:re than 30 days, prepare and submit a $pecial Report to the Comission pursuant to Specification 6.9.2 within the nemt 10 days outlining the cause of the malfunction and the plans f or restcring the instNfhent(s) to OPERABLE status,
- b. TheprovisionsofSpecificationk3.0.3M?.E'arenotapplicable.
SURVE!LL ANCE . REQUIREMENTS
)
4.3.7.2.1 Each of the above required seismic monitoring instruments shall be demonstrated OPERABLE by the perforstnce of the CHANNEL CHECK, CHANNEL FUNO-T10NAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.7.2-1. . 4.3.7.2.2 Each of the above required seismic monitoring instrueents actuated during a seismic event greater than or equal to10.01 g shall be restored to OPERABLE ststus within 24 hours and a CHANNEL CALIBRATION perfomed within 5 days following the seismic event. Data shall be retrieved from ac.f.uated instruments 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 pays describing the magnitude, frequency spectrum and resultant effect upon unit features important to safety. s': . GRAND CULF-UNIT 1 3/4 3-63 AMiaW -
pim Nt. ss -on
. l t
lNSTRUMENTATION METEOROLOGICAL MONITORING ']) LTfn hTAT'JH ! r LIMITING CONDITION FOR OPERATION 4 3.3.7.3 The seteorological monitoring instrumentation channels shown in Table 3.3.7.3 1 shall be OPERABLE. i APPLICAllLITY: At all times. . s' ACT10N: *
.. With one or more required meteorological monitoring instrumentat, ion 1 channels inoperable for more than 7 days, prepare and subit a ! Special Report to the Comission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the instrumentation to OPERABL! status.
i ' 1 j b. The provisions of Specificationk 3.0.3 nd *.t.' are not applicable. 4 ' - . j ,
. . ; $URVE1LLANCE REQUIREMENTS i
! 4.3.7.3 Each of the above required meteorological sonitoring instrumentation
- channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK i and CHANk!L CALIBRATION operations at the frequencies shown in Table 4.3.7.3-1.
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- e.
) l i . } l l? . l . i, cR,ANO cutr UNITI 3,4 3-66 beh - r
Pill ML SI *Cl INSTRUMENTATION TRAVERSING IN-CORE PROCE SYSTEM LIMITING CONDITION FOR OPERATION 3.3.7.7. The traversing in-core probe system shall be OPERABLE with:
- a. Five movable detectors, drives and readout equipment to map the core, and
- b. Indexing equipment to allow all five detectors to be calibrated in a common location.
APPLICABILITY: When the traversing in core probe is used for:
- a. Recalibration of the LPRM detectors, and b." Monitoring the APLHGR, LHGR, HOPR, or MFLPD.
ACTION: With the traversing in-core probe system inoperable, do not use the system for licable monitoring or calibration functions. The provisions of the Specificationabove app \ 3.0.3 :-d 2.C. " are not applicable. SURVEILLANCE REQUIREMENTS 4.3.7.7 The traversing in-core probe system shall be demonstrated OPERABLE by normalizing each of the above required detector outputs within 72 hours prior to use when required for the LPRM calibration function.
"Only tne oetector(s) in the location (s) of interest are iequired to be OPERABLE.
l l 1 GRAND GULF-UNIT 1 3/4 3-78 AMOGT . o. I
INSTRUM!NTATION FIRE DETECTION INSTRUMENTAi!0N , L1MITIN*, CONDITION FOR OPERATION 3.3,7.9 As a sintrue the fire detection instrumentation for each fire detection zone shown In Table 3.3.7.t-1 stall be OPERABLE. APPL 1cABILITY: Whenever equipment protected by the fire detection instrument is required to be OPERABLE. , ACT!0N: . With the ne.ber of OPERABLE Function A or Function B fire detection instroents less than the Minime. Instrueents OPEP.A!LF, requirement of Table 3.3.7.91:
- a. establish a fire watch patrol to inspect the zone (s)
Within I hour, with the Funct ion A or room (s) with function B inoperable instru-pent (s) at least once per hour, unless the instraent(s) is located inside the containsent, steam tunnel or drywell, then inspect tid primary contaiteent at least once per 8 hours or sonitor the contain-ment, steam tunnel and/or drywell air tesperature at least once per hour at the locations listed in Specification 3.7.8, 4.6.1.8 and 4.6.2.6.
- b. Restore the minir.vt nurber of instruments to OPERABLE status within 14 days or preptre and submit a Special Report to the Coestission pur-suant to Specification 6.9.2 within 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the instrument (s) to CPEP.ASLE statut
- c. The provisions of Specificationk 3.0.3 xd 2.0,i are not applicable.
1 SURVE!LLAN:E REQUIREFENTS 4.3.7.9.1 Each of the above required fire detection instroents which are accessible during unit operation shall be demonstrated OPERABLE at least once per 6 months by perforsance of a CHANNEL FUNCTIONAL TEST. Fire detectors which are not accessible during unit operation shall be deronstrated OPERA 8LE by the performance of a CKANNEL FUN:TIOKAL TEST during each COLD SH'JTDOWN exceeding 24 hours unless performed in the previous 6 months. 4.3.7.9.2 The NFPA Standard 720 supervised circuits supervision associated tith the detector alares of sich of the above required fire detection instruments shall be demonstrated OPERA!LE at least once per 6 months. GRAND GULF-UNIT 1 3/4 3 80 bsvepaws k - _m__ m
. - - - - - - ~ ~ * * * * - * '
* *~' * * ^ ~ ~ ~ ~ ' ' * * *
. . . . . . _ ,..m
fil9 NL 91 -01 [ INSTRUMENTATION i IMSE PART DETECTION SYSTEM i LIMITING CONDITION FOR OPERATION 3.3.7.10 The loose part detection system shall be OPERABLE. j t APPLICA8!LITY: OPERATIONAL CONDITIONS 1 and 2. i ACTION:
- a. Witt. ane or more loose part detection system channels inoperable for more than 30 days, prepare and submit a Special Report to the Commis- i sion pursuant to malfunction Specification 6.9.2 withinfor therestoring next 10 the days outlining) the cause of the and the plans channel (s (
to OPERABLE status,
'The provisions of Specification 3.0.3 :-d 1 0." are not applicable.
i b. SURVEILLANCE REQUIREMENTS 4.3.7.10 Each channel of the loose-part detection system shall be demonstrated CPERABLE by performance of a:
- a. CHANNEL CHECK at least once per 24 hours,
- b. CfANNEL FUNCTIONAL TEST at least once per 31 days, and
- c. CHANNil CALIBRATION at least once per 18 months. ,
NL BS Ct Pl%0 INSTRUMENTATION h" ' RADI0 ACTIVE LIQUID EFFLUENT W)NITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.11 The radioactive liquid ef fluent monitoring instrumentation channels
.rwn in Table 3.3.7.;1-1 shall be OPERABLE with their alare/ trip setpoints h; to ensure that the limits of Specifici; tion 3.11.1.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (00CM).
APPLICABILITY: At all times. ACTION:
- a. With a radioactive liquid ef fluent monitoring instrumentation channel i aiarm/ trip setpoint less conservative than requireo by the above ,
specification, iecediately suspend the release of radioactive liquid ' i
/ effluents r.onitored by the affected chennel or declare the channel inoperable.
- b. With lass than the minimum number of radioactive liquid ef fluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7.11-1. Restore the inoperable instrumentation to 0lf RABLE status within the time specified in the ACTION and, if un.accessful, explain why this inoperability was not corrected in a
( timely manner in the next Semiannual Radioactive Effluent Release Report.
- c. The provisions cf Specification 3.0.3-= d 2.0 ' are not applicable.
SURVE!LLANCE REQUIREMENTS 4.3.7.11 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CAtlBRATION and CHANNEL FUNCTIORAL TEST operations at the i f requencie' shown in Table 4.3.7.11-1. 1 1 i i GRAND GULF-UNIT 1 3/4 3 91 ggy 6, l
g g .g a , TABLE 3.3.8 ; (Continued) n PLANT SYSTEMS ACTUATION INSTRUMENTATI0ri
- [L.%
rS ACTION ACTION 130 - a. With the number of OPERABLE channels one less than required by the Minimum OPERABLE Channels per Trip System requirement, plate the inoperable channel in the tr)pped condition within one hour; otherwise, declare the associated containment spray system inoperable and take the action required by Tech-nical Specification 3.6.3.2.
- b. With the number of OPERABLE channels two less than required by the Minimum OPERABLE channels per Trip System require-ment, declare the associated containment spray system inoperable and take the action required by Technical Specification 3.6.3.2.
ACTION 131 - With the number of OPERABLE channels less than required by the Minimum OPERAB'.E Channels per Trip System requirement, restore the inoperable channels to OPERABLE status within one hour; other-t wise, declare the associated containment spray system inoperable and take th. sction required by Technical Specification 3.6.3.2. ACTION 132 - For the feedwater system / main turbine trip system:
- a. With the number of OPERABLE channels one less than required by the Minimum OPERABLE Channels requirement, restore the inoparable channel to OPERABLE status within 7 days or te in at least STARTUP within the next 6 hours,
( b. With the number of OPERABLE channels two less than required by the Minimum OPERABLE Channels per Trip System require-ment, restece at least one of the inoperable channels to OPERABLE status within 72 hours or be in at least STARTUP within the next 6 hours. ACTION 133 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, declare j the associated suppresson pool makeup system inoperable and l take the action required by Specification 3.6.3.4.
. ACTION 134 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, restore the inoperable channels to OPERABLE status within 8 hours; other-wise, declare the associateJ suppression pool makeup system l inoperable and take the action required by Specification 3.6.3.4.
ACTION 135 - With the number of OPERABLE channels less than required by the i Minimum OPERABLE Channels per Trip Function requirement: l a. With one channel inoperable, place the i operable channel l in the tripped condition within one hour or declare the l associated system (s) iroperable. l b. With more than one channel inoperable, declare the i associated system (s) inoperable.
. \'-
i Id y i v v i s i v I.) Of bpCCf'iCOI CI ). . IIO YI Ih[ CI O. GRA,0 GULF-UNIT 1 3/4 3-107 L u e 9 n d., L.
~
Elik;L NL SS of REACTOR COOLANT SYSTEM 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3,4.7 Two main steam line isolation valves (MSIVs) per main steam line shall be OPERABLE with closing times greater than or equal to 3 and less than or ea"al to 5 seconds.
../LICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.
ACTION _:
- a. With one or more MSIVs inoperable:
- 1. Paintain at least one MSIV OPERABLE in each affected main steam line that is open and within 8 hours, either:
' Restore the inoperable valve (s) to OPERABLE status, or a) b) Isolate the affected main steam line by use of a deactivated MSIV in the closed porition.
- 2. Otherwise, be in at least HOT SHUTOOWN within ne next 12 hours and in COLD SHUTOOWN within the following 24 hour',
- 5. The peittent o' Specf*fcatter 2.0.A x- n:t :pp1f::51:. -
SURVEILLANCE REQUIREMENTS 4.4.7 Each of the above required MSIVs shall be demonstrated OPERABLE by verifying full closure between 3 and 5 seconds
- when tested pursuant to Specification 4.0.5. The provisions of Specification 4.0.4 are not appifcable for entry into OPERATIONAL CONDITIONS 2 or 3 provided the surveillance is performed within 12 hours af ter reaching a reactor steam pressure of 600 psig and prior to entry into OPERATIONAL CONDITION 1.
*The 3 seconds is the time meacured from start of valve motion to complete valve :losure. The 5 seconds is the time measured from initiation of the actuating signal to complete valve closure.
GRAND GULF-UNIT 1 3/4 4-24 b e e n ' No. -
WL SS -ol P173 . AEACTOR COOLANT SYSTEM 3/4.4.8 STRUCTURAL INTEGRITY r LIMIT!fG ITION FUR OPERATION i 3.4.8 The structural integrity of ASE Code Class 1, 2 ar.J 3 campounts shall be saintained in accordance with Specification 4.4.8. ' APPLICA81LITY: OPERATIONdL C00CITIONS 1, 2, 3, 4 and 5. ACTION:
- a. With tha structural integrity of any ASE 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 Systes temperature more than 50'F above th= minimum temperature required by NOT considerations,
- b. With the structural integrity of any ASME Code Class.2 component (s) not conforming to the above requirteents, restore the structural integrity of the affected component (s) to within its Itait or isolatp the affected component (s) prior to increasing the Reactor Coolant i Systes 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 it lisit or isolatlt the affected cosponent(s) from service.
{. . i i
- d. 'he previ+4:n: ef- Spelfication 3.0.' : : r. t ;;He:hh.
SURVEILLANCE REQUIREMENTS 4.4.8 No requirements other than Specification 4.0.5. l l 1 l l l l GRAND GULF UNIT 1 3/4 4-25 be,JcKewt We, t __ ^
NL SE - 01 PIM REACTOR COOLANT SYSTEM
?[ COLD SMUT 00W .
LIMITING CONDITION FOR OPERATION 3.4.9.2 Two# shutdown cooling mode loops of the residual heat removal (RHR) system shall be OPERABLE and, unless at least one re:irculation pump is in operation, at least one shutdown cooling mode loop shall be in operation *'" with 6ach loop consisting of at least:
- a. One OPERABLE RHR pump, and
- b. One OPERABLE RHR heat exchanger.
AoPLICASILITY: OPERATIONAL CONDITION 4. ACTION:
- a. With less than the abov6 required RHR shutdown cooling mode loops OPERABLE, within one hour and at least once per 24 hours thereaf ter, demonstrate the operability of at least one alternate method capable of decay heat removal for each inoperable RHR shutdown cooling mode loop.
- b. With no RdR shutdown cooling mode loop in operation, within one Pour establish reactor coolant circulation by an alternate method and monitor d.~ reactor coolant temperature and pressure at least ance per hour.
sea ..-. -- se..m*- **
, n. m 4,4 m m m< e..,4<<,..<m-SURVEILLANCE REQUIREMENTS 4.4.9.2 At least one shutdown cooling mode loop of the residual heat removal system or alternate method shall be determined to be in operation and circulating reactor coolant at least once per 12 hours.
'One RHR shutdown cooling moet loop may be inoperable for up to 2 hours for surveillance testing provided the other loop is OPERABLE and in operation.
"The shutdown cooling pump may be removed from operation for up to 2 hours per 8 hour period provided the other loop is OPERABLE.
HThe shutdown cooling mode loop may be removed from operation during hydrostatic testing. ( **Thh ::ct;thr b :pp!H:51: =t!' :tutup f r:- th; ;;; cad refeelin; eute;r.- 3/4 4-27 Asendnent No. 36,- GRANO GULC-UNIT 1
, N L 31 -0l e -
EMERGENCY CORE COOLIN'G SYSTEMS 3/4 5.2 ECCS - SHUTDOW LIMITING CONDITION FOR OPERATION 3.5.2 At least two of the following shall be OPERABLE:
- a. The low pressure core spray (LPCE) system with a flow path capable of taking suction from the suppression pool and transferring the water through the spray sparger to the reactor vessel.
- b. Low pressure coolant injection (LPCI) subsystem "A" of the RHR system with a flow path capable of taking suction from the suppression pool upon being manually realigned and transferring the water to the reactor vessel,
- c. Low pressure coolant injection (LPCI) subsystem "B" of the RHR syster with a flow path capable of taking suction from the suppression pool
- upon being manually realigned and transferring the water to the reactor vessel.
d. Low pressure coolant injection (LPCI) subsystem "C" of the RHR system with a flow path capable of takin~g suction from the suppression p;ol upon being manually realigned and transferring the water to the reacter vessel.
- e. The high pressure core spray (HPC',) systu with a flow path capable of taking suction from one of the following water sources and trans-ferring the water through the spray sparger to the reactor vessel:
( 1. From the suppression pool, or
- 2. When the su*pression pool level is less than the limit or is drained, frem the condensate storage tank co..taining &t least 170,000 available gallons of water, equivalent to a level of 18 feet.
APPLICABILITY: OPERATIONAL CONDITION 4 and 5*. ACTION:
- a. With one of the above required subsystems / systems inoperable, restore at least two subsystems / systems to OPERABLE sta,tus within 4 hours or suspend all operations that have a potential for draining the rea g r i vessel. h e-p :.': Er: ef !?::Uk:th 2.0.' ;r: rr. :.;;' i::b h . l
- b. With both of the above re:vi ed subsyste s/ systems in:eaatle, sus;ead CORE ALTERATIONS an: all c;trations that have a potential for draining the reactor vessel. Restore at least one subsystem / system to OPERABLE status within 4 hours or establish SECONDARY CONTA:WENT INTEF ITY h_ are not pemitted, fwitrin the next S nourshEP510NA
^
The ECCS is not required to be OPERABLE provided that the reactor vessel heae
is removed, the cavity is flooded, the reactor cavity and transfer canal gates
'in the upper containment pool are re oved, and water level is maintained wit *.in '
the limits of Specifications 3.9.8 and 3.9.9.
': exceptiw b wiksh n;il eterb; fic tM ;e;eM r;f-;'h; ;d;;;
l GRAND GULF-UNIT I 3/4 5 6 Amend ent Nc. 42,- - l
1
. ,. 9 L %B -01 P G6 EMERGENCY CORE COOLING SYSTEMS 3/4.5.3 SUPPRESSION POOL LIMITING CON 0! TION FOR OPERATION -
3.5.3 The suppression pool shall be OPERABLE:
- a. In OPERATIONAL CONDITION 1, 2 or 3 vith a contained water volume of at least 135,291 ft2, equivalent to a level of 18'4-1/12."
b. In OPERATIONAL CONDITION 4 or 5" with a contained water volume of at least 93,600 ft2, equivalent to a level of 12'8", except that the suppression pool level may be less than the limit or may be drained provided that:
- 1. No operations are performed that have a potential for draining the reactor vessel,
- 2. The reactor mode switch is locked in the Shutdown or Refuel position,
- 3. The condensate storage tank contains at least 170,000 available gallons of water, equivalent to a level of 18', and
- 4. The HPCS system is OPERABLE per Specification 3.5.2 with an OPERABLE flow path capable of taking suction from the condensate storage tank w and transferring the water through the spray sparger to the reactor venel. .
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3, 4 and 5^.
; ACTION:
- a. In OPERATIONAL CONDITION 1, 2 or 3 with the suppression pool water level less than the above limit, restore the water level to within the iimit within 1 hour or be in at least NOT SHUT 00WN within the
, next 12 hours and in COLD SHUT 00VN within the following 24 hours.
- b. In OPERATIONAL CONDITION 4 or 5" with the suppression pool water level less than the above limit or drained and the above required conditions not satisfied, suspend CORE ALTERATIONS and all opera-tions that have a potential for draining the reactor vessel and lock the reacter mode switch in the Shutecwn posJtien- htW 49 SECONDARY
~ CONTAINMENT INTEGR1TY_within 8 hours./0PERATIONAL C
~
s oYrjecificationIO.'4 are not"perm]tted_. See Specification 3.6.3.1 for pressure suppression requirements. The suppression pool is not required to be OTERABLE provided that the reactor vessel head is removed, the cavity is flooded or being flooded from the suppression pool, the reactor cavity and transfer canal gates in the upper containment pool are removed when the cavity is flooded, and the water level is maintained within the limits of Specification 3.9.8 and 3.9.9. GRAND GULF-UNIT 1 3/4 5-8 Amendment No. 42 L
pt %t 61 , Pin e. CONTAINMENT SYSTEMS ORYWELL AIR LOCK LIMITING CONDITION FOR OPERATION 3.6.2.3 The drywell air lock shall be OPERABLE with:
- a. Both doors closed except when the air lock is being used for normal transit entry and exit through the drywell, then at least one air lock door shall be closed, and
- b. An overall air lock leakage rate of less than or equal to 2 scf per hour at P,, 11.5 psig.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2* and 3. ACTION:
- a. With one drywell air lock door inoperable:
- 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. Operation may then continue provided that the OPERABLE air lock door is verified to be locked closed at least on:e per 31 days. Othe mise, be in at least HOT SHUTOOWN within the next 12 hours and in COLD SHUTOOWN within the following 24 hours.
- 2. S: p e;t:!e- ef Spe:"teet'e- ?.0 ' ere aa+ epp e5'e
- b. With the drywell air lock inoperable, except as a result of an inoperable air lock door, maintain at least one air lock door closed; restore the inoperable air lock to OPERASLE status within 24 hours or be in at least
- HOT SHUTOOWN within the next 12 hours and in COLD SHUTOOWN within the following 24 hours.
- c. With one diywell air lock door inflatable seal system seal pressure r instrumentation channel inoperable, restore the inoperable channel to '
OPERABLE status within 7 days or verify the associated inflatable seal pressure to be 1 60 psig at least once per 12 hours.
"See Special Test Exception 3.10.1, GRAND GULF-UNIT 1 3/4 6-15 Amendment No. 31
NL II-OI , klh 4
' CONTAINMENT SYSTEMS-3/4.6.4 CONTAINMENT AND ORYVELL !$0LAT!0N VALVES LIMITING CONDITION FOR OPERATION 3.6.4 The containment and drywell isolation valves shown in Table 3.6.4-1 shall be OPERABLE with ilation times less than or equal to those shown in Table 3.6.4-1. -
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3, and f. ACTION: With one or more of the containment or drywell isolation valves shown in Table 3.6.4-1 inoperable, maintain at least one isolation valve OPERABLE in . each affected penetration that is open and within 4 hours either:
- a. Restore the inoperable valve (s) to OPERABLE status, or
- b. Isolate each affected penetration by use of at least one deactivated automatic valve secured in the isolated position," or ,'
- c. Isolate each affected penetration by use of at least one closed manual valve or bliad flange."
Otherwise, be in at least HOT SHUT 00VN within the next 12 hours and in COLD SHUT 00VN within the following 24 hours. i "Isolation valves, except MSIVs, closed to satisfy these requirements _say_be reopened on an intermittent basis under administrative controls. f! solation valves shown in Table 3.6.4 1 are also required to be OPERABLE when their associated actuation instrumentation is required to be OPERABLE per Table 3.3.2 1. GRAND GULF-llNIT 1 3/4 6 28 Arendment No. 42 -
p t M-ot pigq INSERT to page 3/4 6-28 OPERATIONAL CONDITION changes, as provided by Specification 3.0.4, are not allowed while isolation valves are open under these administrative controls.
8L 88-01 P(30
. 3/4.7 PLA4i SYSTEMS .
3/4.7.1 SERyICEWNERSYSTEMS
- k. ' STANDBY SERVICE LATER SYSTEM LIMITING CONDIT_'.0N FOR OPERATION (SSW) system 3.7.1.1 Ea h of ti.* fo11 ewing th each subsystem comprised of:
subsystems s>all be b?ERABLE *a. independent standby service
- a. One 07! TABLE SSw pump and
- b. An OPERABLt ik. p a n capable of taking suction from the associatee SSW cooling tower basin and transferring the water through the RHR heat exchangers and to associated plant equipment, as required, shall be OPERABLE as follows:
- 1. In OPERATIONAL CONDITIONS 1, 2, and 3: two subsys'tems; and
- 2. In OPERATIONAL CON"JITIONS 4, 5, and *: the subsystems asso:iated with the systems and components required to be OPERABLE by Specifications 3.4.9.2, 3.5.2, 3.8.1.2, 3.9.11.1 or 3.9.11.2.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3, 4, 5 and *. ACTION:
- a. In OPERATIONAL CONDITION 1, 2 or 3:
1. With one SSW subsystem inoperable, restore the inoperable sub-
- system to OPERABLE status within 72 hours or be in at least HOT SHUT 00dN within the next 12 hours and in COLD SHUTOOWN withi
/. the following 24 hours.
1 2. With both SSW subsystems inoperab*e, be in at least HOT SHUTOOWN within the next 12 hours and in COLD SHUT 00WN'* within the folio.ing 24 hours.
- b. In OPERATIONAL CONDITION 3 or 4 with the SSW subsystem, which is asso-ciated with an AHR loop required OPERABLE by Specification 3.4.9.1 or 3.4.9.2, inoperable, declare the associated RHR loop inoperable and take the ACTION required by Specification 3.4.9.1n:t or 3.4.9.2,
- p;1!::Has : f:- appli-cable. -ke-; :'ef:!:n: Of Sp::f 'f e'"
;ntry inte.4 PEP.'T:CF% C00:T 0F %:r 3.0.' : :
- c. In OPERATIONAL CONDITION 4 or 5 with the SSW subsystem, which is asso-ciated with an ECCS pump required OPERABLE by Specification 3.5.2, inoperable, declare the associated ECCS pump inoperable and take the ACTION required by Specificat Q n 3.5.2. -Th: pr;vi:!:n: :1 !;::!'!:e-
=tt:r 3.0. ' s e W
- ppt ia akt a K t When handling irradiated fuel in the primary or secondary containment.
am
.* Whenever both SSW subsystems are inoperable, if unable to attain COLD SHUT 00^
- as required by this ACTION, paintain reactor coolant temperature.as low as '
practical by use of alternate heat removal methods. '
# nie Eace;ti;n ie ;;;15::51: et" t:-t.p f r; th: :::;nd r:'.:1! ; ::t:; w i
O 3/4 7-1 Amendment No. 3I,- GRAND GU'.F-UNIT 1 , - - - - - . , , . --_.-----_,,-,--,,--.-------,---,-n.,e, , , - . , . - - . , . - - , , , - - - - - , , , , , - - - - - - - - -
Pl31 NL B6001 PLANT SYSTEMS LIMITING CONDITION FOR OPERATION ACTION: (Continued)
- d. In OPERATIONAL CONDITION 5 with the SSV subsystem, which is associatec with an RHR system required OPERABLE by Specification 3.9.11.1 or 3.9.11.2, inoperable, declare the associated ?wR system inoperable and take the ACTION required by Specification 3.3.11.', or 3.9.11.2, asapplicabje. Th: pr:;i:!:n: f Sper!'f ettie- ?.0.' : : net 2;;1I::b!!.
- e. In OPERATIONAL CONDITION 8, with the 55V subsystem, which is asse:iatec with a diesel generator required OPERABLE by Specification 3.8.1.2, inoperable, declare the associated diesel generator inoperable and take the ACTION required by Specification 3.8.1.2. The provisions of Specification 3.0.3 are not applicable.
- f. In OPERATIONAL CONDITIONS 1, 2, 3, 4, or 5 with the $$V subsystem, which is associated with a diesel generator required OPERABLE by Specification 3.8.1.1 or 3.8.1.2, inoperable, declare the associated diesel generator inoperable and take the ACTION required by Specification 3.8.1.1 or 3.8.1.2 as applicable.
F- SURVEILLANCE REQUIREMENTS _ 4.7.1.1 At least the above required standby service water system subsystem (s) shall be deaonstrated OPERABLE:
- a. At least once per 31 days by verifying that each valve in the flow ,
l path that is not locked, sealed or otherwise secured in position, is in its correct position. l
- b. At least once per 18 months during shutdown by verifying that each automatic valve servicing safety related equipath'. actuates to its correct position on an actuation test signal.
l l - 'Tht: :: cept!:- 1: :;;14r.:b!: ent!' :tertup '-e- th: e e: ^ f e f ee"'; SU' ';+ GRANO GULF-UN;T 1 3/4 7 2 Aaendaent Nc. II. 3!,
P t33 NL 19 -31 PLANT SYSTEMS h-- 3/4.7.5 SEALEDSOURCECONTAMINATIOy LIMITING CONDITION FOR OPERATION 3.7.5 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 10 microcuries of alpha emitting material shall be free of greater than or equal to 0.005 microcuries of removable contamination. APPLICABILITY: At all times. ACTION:
- a. With a sealed source having removable contamination in excess of the ebove limit, withdraw the sealed source from use and either:
- 1. Decontaminate and repair the sealed source, or
- 2. Dispose of the sealed source in accordance with Commission Regulations.
- b. The provisions of Specification \ 3.0.3-=d 2.0.' are not applicable.
[ SURVEILLANCE REQUIREMENTS 4.7.5.1 Test Reauirements - Each sealed source shall be tested for leakage and/or containination by:
- a. The licensee, or
- b. Other persons specifically authorized by the Commission or an Agreenent State.
The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample. l ! 4.7.5.2 Test Fr#quencies - Each category of sealed sources, excluding startup sources end fission detectors previously subjected to core flux, shall be tested at the frequency described below. l a. Sources in use - At least once per six months for all sealed sources containing radioactive material: I 1. With a half-life greater than 30 days, excluding Hydrogen 3, and
- 2. In any form other than gas.
e GRAND GULF-UNIT 1 3/4 7-15 W N. - l l L
~ WL SUot PLANT SYSTEMS 3/4.7.6 FIRE SUPPRESSION SYSTEMS (. ... . FIRE SUPPRESSION WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.6.1 The fire suppression water system shall be OPERABLE with:
- a. At least two OPERABLE fire suppression fire pumps, each with a capacity of 1500 gps, with their discharge aligned to the fire suppression header,
- b. Separate fire water storage tanks, each with a minimum contained volume of 210,000 gallons, and
- c. An OPERABLE flow path capable of taking suction from the "A" fire water storage tank and the "B" fire water storage tank and transferring the water through distribution piping with OPERABLE sectionalizing i control or isolation valves to the yard hydrant curb valves, the last valve ahead of the water flow alarm device on each sprinkler or hose standpipe and the last valve ahead of the deluge valve on each deluge or spray system required to be OPERABLE per Specifications 3.7.6.2, 3.7.6.5, and 3.7.6.6.
. APPLICABILITY: At all times.
ACTION:
- a. With one of the above required fire pumps and/or one fire water storage
- tank inoperable, restore the inoperable equipment to OPERABLE status within 7 days or provide an alternate backup pump or supply. The provisions of Specification \ 3.0.3 u,4 2.0.i are not applicable.
I
- b. With the fire suppression water system otherwise inoperable, establish l a backup fire suppression water system within 24 hours.
SURVEILLANCE REQUIREMENTS 4.7.5.1.1 The fire suppression water system shall be demonstrated OPERA 8LE: l a. At 1c3st once per 7 days by verifying the minimum contained water j supply volume. l b. At least once per 31 days by starting the electric motor driven fire suppression pump and operating it for at least 15 minutes. l c. At least onct per 31 days oy verifying that each valve, manual, power t operated or automatic, in the flow path is in its correct position,
- d. At least once ptr 12 months by cycling each testable valve in the
.- flow path through at least one complete cycle of full travel.
GRAND GULF-UNIT 1 3/4 7-17 L
PlYt i
- m. SS ol
. PLANT SYSTEMS SPRAY AND/OR SPRINKLER SYSTEMS LIMITINC CONDITION FOR OPERATION L.
3.7.6.2 The following spray / sprinkler systems shall be OPERABLE:
- a. Diesel Generator Building
- 1. Diesel Generator A pre-action sprinkler system N1P640142A
- 2. Diesel Generator B pre-action sprinkler system N1P640142B
- 3. Diesel Generator C pre-action sprinkler system N1P640142C
- b. Auxiliary Building *
- 1. Elevation 93'/103' Northeast Corridor N1P64D150
- 2. Elevation 119' Northeast Corridor N1P64D151
' 3. Elevation 139' Northeast Corridor N1P64D152
- 4. Elevation 166' Northeast Corridor N1P640153
- 5. Elevation 119' West Corridor N1P640158
- 6. Elevation 139' West Corridor N1P640159 Elevation 166' Northwest Corridor N1P640162 7.
- c. Control Building * ;
Elevation 148' Lower Cable Room N1P64D154 1. Elevation 189' Upper Cable Room N1P640155 2. Elevation 93' NSP640140 3. Fire Pump House
- NSP640136A/B d.
APPLICABILITY: Whenever equipment protected by the spray / sprinkler systems is required to be OPERABLE. ACTION:
- a. With one or more of the above required spray and/or sprinkler systems inoperable, within one hour establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol.
- b. The provisions of Specification 3.0.3 =f La ' are not applicable.
SURVEILLANCE REQUIREMENTS 4.7.6.2 The above required spray and sprinkler systems shall be demonstrated OPERABLE: ., power
- s. At least once per 31 days by verifying that each valve, manual, ion.
operated or automatic, in the flow path is in its correct posit "Wet pipe sprinkler system. 3/4 7-20 Amendment No. 15,- GRAND GULF-UNIT 1
P13E hh. 69 -61 PLANT SYSTEMS g2 SYSTEMS LIMITING CONDITION FOR OPERATION , i 3.7.6.3 The following low pressure C0; rystemt shall be OPERABLE-location System Nutttber Area Auxiliary Bldg. E1. 139'0" N1P64D201A, B, C, D Electrical Penetration Room Auxiliary Bldg. E1. 119'0" N1P640200A, B, C, D Electrical Penetration Room Control Cabinet Room Control Bldg. El. 189'0" N1P64D216 Division I Switchgear Room Control Bldg. E1. 111'0" N1P640207 Division III Switchgear Room Control Bldg. E1. 111'0" N1P640209 Division II Switchgear Room Control Bldg. E1. 111'0" N1P64D208 Emergency Shutdown Panel Rm Control Bldg. E1.111'0" N1P640212
- Motor Generator Room Control Bldg. El. 148'0" N1964D2148 i
Auxiliary aldg. E1. 166'0" N1964D217A, B Electrical Switchgear Room Lower Cable Spreading Room Control Bldg. El. 148'0" N1P64D213 Upper Cable Spreading Room Control Bldg. El. 189'0" N1P640215 , APPLICABILITY: Whenever equipment protected by the CO2 systems is required to be OPERABLE. ACTION:
- a. With one or more of the above required CO, systems inoperable, within one hour establish a continuous fire waten with backup fire suppres-sion equipment for those areas in which redundant systems or components could be danaged; for other areas, establish an hourly fire watch patrol.
- b. The provisions of Specification 3.0.3-nd 2.0.' are not applicable.
a 3/4 7-22 swo*%f No, l GRAND GULF UNIT 1 -
, - - . . - - - - , - . , , _ , , . . , . - , , -.-,-,----------n----,--m _.w--., , _ - - - - - - - - - - - -
f. 913b NL st ot PLANT SYSTEMS HALON SYSTEMS . LIMITING CONDITION FOR OPERATION 3.7.6.4 The fol',owing Halon systems shall be OPERABLE with the storage tanks having at least 95% of full charge weight and 90% of full charge pressure:
- a. N ntrol Building, elev. 148'0", Computer and Control Panel Room
- t. Control Building, elev.166'0", PGCC Under Flcor Area
- c. Control Cabinet Room, elev.189'0", PGCC Under Floor Area APPLICABILITY: Whenever equipment protected by the Halon systems is required to be OPERABLE.
ACTION:
- a. With one or more of tht above required Halon systems inoperable, within one hour establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol.
- b. The provisions of Specificationk 3.0.3 cd 10 ' are not applicable.
SURVEILLANCE REQUIREMENTS 4.7.6.4 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, except for hazard area selector valves F497G and F497H, in the flow path is in its correct position.
- b. At least once per 6 months by verifying Halon storage tank weight and pressure.
- c. At least once per 18 months by:
- 1. Verifying that the system, including associated ventilation system fire damper logic, actuates automatically upon receipt of a simulated actuation signal (Actual Halon release, Halon bottle initiator valve actuation, and electro-thermal link burning may be excluded from the test), and
- 2. Performance of a flow test through headers and nozzles to assure no blockage, and
- 3. Exercising each ventilation system fire damper to the closed position and verifying the dampers move freely.
GRAND GULF-UNIT 1 3/4 7-24 a sur
9137 NL SS-ci PLANT SYSTEMS
;.' FIRE HOSE STATIONS .
LIMITING CONDITION FOR OPERATION 3.7.6.5 The fire hose stations shown in Table 3.7.6.5-1 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 3.7.6.5-1 inoperable, route an additional fire hose of equal or greater diameter to the unprotected area (s) from an OPERABLE hose station within 1 hour if the inoperable fire hose is the primary means of fire suppression; otherwise, route the additional hose within 24 hours.
- b. TheprovisionsofSpecification\3.0.3MLnA are not applicable.
SURVEILLANCE REQUIREMENTS 4.7.6.5 Each of the fire hose stations shown in Table 3.7.6.5-1 shall be demonstrated OPERABLE: I At least once per 31 days by a visual inspection of the fire hose a. stations accessible during plant operation to assure all required equipment is at the station,
- b. At least once per 18 months by:
- 1. Visual inspection of the fire hose stations not accessible during l plant operation to assure all-required equipment is at the station.
l 2. Removing the hose for inspection and re-racking, and
- 3. Inspecting all gaskets and replacing any degraded gaskets in l the couplings.
f l c. At least once per 3 years by:
- 1. Partially opening each hose station valve to verify valve OPERABILITY and no flow blockage.
l
- 2. Conducting a hose hydrostatic test at a pressure of 150 psig or at l least 50 psig above the maximum fire main operating pressure, j whichever is greater, i
([' GRAND GULF-UNIT 1 3/4 7-25 Awwawbn . e.
Pl3& HL M -o1 PLANT SYSTEMS YARD FIRE HYDRANTS AND HYORANT HOSE HOUSES LIMITING CONDITION FOR OPERATION 3.7.6.6 The yard fire hydrants and associated hydrant hose houses shown in Table 3.7.6.6-1 shall be OPERABLE. i APPLICABILITY: Whenever equipmcn'. in the areas protected by the yard fire hydrants is required to be OPER/F.5. l ACTION:
- a. With one or more of the yard fire hydrants or associated hydrant hose houses shown in Table L 7.6.6-3 inoperable, route sufficient additional lengths of fire hose of equal or greater diameter located in an adjacent s
OPERABLE hydrant hose hause to provide service to the unprotected area (s)
' within 24 hours, The provisions of Specificationk 3.0.3 rd ^." are not applicable.
b. SURVEILLANCE REQUIREMENTS 4.7.6.6 Each of the yard fire hydrants and asse:iated hydrant hose houses shown in Table 3.7.6.6-1 shall be demonstrated OPERABLE:
- a. At least once per 31 days by visual inspection of the hydrant hose house to assure all required equipment is at the hose house,
- b. At least once per 6 months, during March, April or iiay and during September, October or November, by visually inspecting each yard fire '
hydrant and verifying that the hydrant barrel is dry and that the hydrant is not damaged.
- c. At least once per 12 months by:
- 1. Conducting a hose hydrostatic test at a pressure of 150 psig or at least 50 psig above the maximum fire main operating pressure whichever is greater.
- 2. Rr. placement of all degraded gaskets in couplings.
- 3. Performing a flow check of each hydrant.
GRAND GULF-UNIT 1 3/4 7-28 b,
913 9 NL SS-01 PLANT SYSTEMS 3/4.7.7 FIRE RATED ASSEMBLIES LIMITING CONDITION FOR OPERATION 3.7.7 All fire rated assemblies (walls, floor / ceilings, cable tray enclosures and other fire barriers) separating safety related fire areas or separating portions of redundant systems important to safe shutdown within a fire area, and all sealing devices in fire rated assembly penetrations (fire doors, fire windows, fire dampers, cable and piping penetration seals and ventilation seals) shall be OPERABLE. APPLICABILITY: At all times. ACTION:
- a. With one or more of the above required fire rated assemblies and/or sealing devices inoperable, within one hour establish a continuous
' fire watch on at least one side of the affected assembly (s) and/or sealing device (s) or verify the OPERABILITY of fire detectors on at least one side of the inoperable assembly (s) and/or sealing device (s) and establish an hourly fire watch patrol,
- b. The provisions of Specification \ 3.0.3 =d 2.0.' are not applicable.
SURVEILLANCE REQUIREMENTS 4.7.7.1 Each of the above required fire rated assemblies and sealing devices shall be verified OPERABLE at least once per 18 months by performing a visual inspection of:
- a. The exposed surfaces of each fire rated assembly.
- b. Each fire window / fire damper and associated hardware.
t c. At least 10 percent of each type of sealed penetration. If apparent I changes in appearance or abnormal degradations are found, a visual inspection of an additional 10 percent of each type of sealed penetration shall be made. This inspection process shall continue l l until a 10 percent sample with no apparent changes in appearance er abnormal degradation is found. Samples shall be selected so that each penetration seal will be inspected at least once per 15 years, l l l 3/4 7-30 wT j GRAND GULF-UNIT 1
N t M-01 pige t ELECTRICAL P0h!R SYSTEMS
'3/4.8.7 0.C. SOURCES l 0.C. $0Uttt$ - CPERATING LIMITING CON 0!TIQN FOR OPERATION 3.8.2.1 As a nintem, the following 0.C. electrical power sources shall be
- opt 0ABLI: .
- a. Olvision 1, consisting of:
- 1. 125 volt battery 1A3.
- 2. 125 volt full capacity charger 1A4 er 1AS.
. b. Olvision 2, consisting of:
- 1. 125 volt battery 183,
- 2. 125 volt full capacity charger 184 or 135,
- c. Olvision 3, consisting of:
- 1. 125 volt battery 1C3.
- 2. 125 volt full capacity charger 1C4.
APPLICAI!LITY: CPERATIONAL CONDITIONS 1, 2 and 3. ACTION: .,
- s. With either Olvision 1 battery or Division 2 battery of the above required 0.C. electrical power sources inoperable,. restore the inoperable division battery to CPERABLE status within 2 hours or be -
in at least HOT $HUTOCW within the next 12 hours and in COLO $HUTCChN within the following 24 hours,
- b. With Division 3 battery of the above required 0.C. electrical power i sources inoperable, declare the HPCS system inoperaale and take the ACTION requind by Specification 3.5.1.
- c. With one of the above required full capacity chargers inoperable, demonstrate the OPERA 31LITf of its associated battery bank by i
performing Surveillance Requironent 4.8.2.1.a.1 within one hour and at least once per 8 hours thereaf ter. If any Category A limit in Table 4.8.2.1 1 is not set, declare the_ battery op ab OPERATIONAL C0fiDITI0f( changes per Specification 3.0.4 1 A' are not permitted. I " - l , m m i l GRAMO CULF* UNIT 1 3/4 4 10 hadmad do. -
NL %3 -01 P RI me a a* ELECTRICAL DCwER SYSTEwS - 0.C. SOURCES SHUTCCwN LIMITING CCNDIT!CN FOR OPERAT!CN 3.8.2.2 As a minimum, Oivision 1 or Olvision 2, and, when the HPC5 System is required to be OPERA 8LE, Division 3, of the O.C. electrical pe=er sources shall be OPERABLE with:
- a. Division 1 consisting of:
- 1. 125 volt eattery 1A3.
- 2. 125 volt full capacity charger 1A4 or 1A5. -
D. Division 2 consisting of:
- 1. 125 volt tattery 183.
- 2. 125 volt full capacity charger 184 or 185.
- c. Division 3 consisting of:
- 1. 125 volt battery 1C3.
2 125 volt full capacity charger 1C4. APPLICABILITY: OPERATIONAL CON 0!TIONS 4, 5 and *. ACTION: .
- a. With both Division 1 battery and Division 2 battery of the above required 0.C. electrical power sources inopersole, suspend CORE ALTERATIONS, handling of irradiated fuel in the primary or secondary containment and operations with a potential for draining the reactor vessel,
- b. With Division 3 battery of the above required 0.C. electrical ao.er sources inoperable, declare the HPCS Systes inoperante and tane tre ACTION required by Specification 3.5.2 and 3.5.3.
- c. With any of the above required full capacity chargers inocerable, demonstrate the OPERA 8!LITY of its associated battery bant ey performing Surveillance Requirement 4.8.2.1.a.1 within one nour and at least once par 8 hours thereafter. If any Category A limit in Table 4.8.2.1 1 is not met, declare the cattery inoperacle.
l
- d. The provisions of Specification 3.0.3 are not applicable.
SURVE!LLANCE REQUIREMENTS 4.9.2.2 At least the above reovired battery and charger sna11 ce cemenstrated CPERABLE per Surveillance Requirement 4.3.2.1. when nandling irradiated fuel in tne primary or secondary containeent. GRAND GULF
- UNIT 1 3/4 6 14 kdfd No,
Nt %841 Pau . lHSERT to page 3/4 8-14 OPERATIONAL CONDITION changes per Specification are not permitted.
NL NM 9143 ELECTRICAL POWER SYSTEMS \ LIMITING CONDITION FOR OPERATION (Continued) ACTION:
- a. For A.C. power distribution:
- 1. With both Division 1 and Division 2 of the above required A.C.
distribution system not energized and/or with the load shedding and sequencing panel associated with the division (s) required to be energized inoperable, suspend CORE ALTERATIONS, handling of irradiated fuel in the primary or secondary containment a , operations with a potential for draining the reactor vessel INSERT 1
- 2. With Division 3 of the above required A.C. distribution system not energized, declare the HPCS system inoperable and take,the ACTION required by Specification 3.5.2 and 3.5.3.
- b. For D.C. power distribution:
- 1. With both Division 1 and Division 2 of the above required D'.C.
distribution system not energized, suspend CORE ALTERATIONS, handling of irradiated fuel in the primary or secondary con-tainment and opera 11.ons with a potential for draining the
~
reactorvessel.TNSEf2)
- 2. With Division 3 of the above required D.C. distribution system not energized, declare the HPCS system inoperable and take the .
ACTION required by Specification 3.5.2 and 3.5.3.
- c. The provisions o ' Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS i 4.8.3.2.1 At least the above required power distributior, system divisions shall be determined energized at least once per 7 days by verifying correct hrester alignment on the busses /LCs/MCCs/ panels and voltage on the busses /LCs. I 4.8.3.2.2 The above required load shedding and sequencing panel (s) shall be i demonstrated OPERABLE:
- a. At least once per 1? hours by determining that the auto-test system is operating and is not indicating a faulted condition.
I b. At least once per 31 days by performance of a manual test and verifying response within the design criteria to the following test inputs: i a) LOCA. b) Bus undervoltage, l Bus undervoltage followed by LOCA. c) d) LOCA followed by bus undervoltage. / . GRMD GULF-UNIT 1 3/4 8-18 bens ei . f ,
NL.N O pl% INSERT to page 3/4 8-18 INSERT 1: OPERATIONAL CONDITION changes per Specification 3.0.4 are not permitted. INSERT 2: OPERATIONAL CONDITION changes per Specification 3.0.4 are not permitted. l l t l
pitG NL St ci ELECTRICAL POWER SYSTEMS 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES h.:./.c. PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES LIMITING CONDITION FOR OPERATION 3.8.4.1 All primary containment penetration conductor overcurrent protective devices shown in Table 3.8.4.1-1 shall be OPERABLE. APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3. ACTION:
- a. With one or more of the primary containment penetration conductor overcurrent protective devices shown in Table 3.8.4.1-1 inoperable, declare the affected system or component inoperable and apply the appropriate ACTION statement for the affected system, and:
- 1. For 6.9 kV circuit breakers, de-energize the 6.9 kV circuit (s) by tripping the associated redundant circuit breaker (s) within 72 hours and verify the redundant circuit breaker to be tripped at least once e per 7 days thereafter.
- 2. For 480 volt circuit breakers, remove the inoperable circuit breaker (s) from service by racking out the breaker within 72 hours and verify the inoperable breaker (s) to be racked out at least once per 7 days thereafter.
< Otherwise, be in at least HOT SHUTDOWN within the next 12 hours and in COLD SHUT 00V1 within the following 24 hours.
mu..,....-+
- 5. rw e p.mut,4c., mr gm.c4<4cp4mn 1 n a ... mm+ .ppu r.hi . +m dtV#c"! #^ 6.9 '" ciPcuit! 'hich h!Y^ th^i" r^dU".d!"t 7 "cui t b""9.0 ?!
4
- u. #h. 4mmp.r x1. c 4.cip + 5..p..
+177 3 er +m aan um1+ c4 cii4+ which h r :k-d :Ut,.
SURVEILLANCE RiQUIREMENTS 4.8.4.1 Each of the primary containment penetration conductor nyercurrent protective devices shown in Table 3.8.4.1-1 shall be demonstrated OPERABLE:
- a. At least once per 18 months:
- 1. By verifying that the medium voltage 6.9 kV circuit breakers are OPERABLE by selecting, on a rotating basis, at least 10% of the circuit breakers and performing:
a) A CHANNEL CALIBRATION of the associated protective relays, and b) An integrated system functional test which includes simulated automatic actuation of the system and verifying that each relay and associated circuit breakers and overcurrent control circuits function as designed and as specified in Table 3.8.4.1-1. (( GRAND GULF-UNIT 1 3/4 8-19 AwemeA I4
REFUEllNG OPERATIONS 3/4.9.10 CONTROL ROD REMOVAL SINGLE CONTROL ROD REMOVAL LIMITING CONDITION FOR OPERATION 3.9.10.1 One control rod and/or the associated control rod drive mechanism may be removed from the core and/or reactor pressure vessel provided that at least the following requirements are satisfied until a control rod and associ-ated control rod drive mechanism are reinstalled and the control rod is fully inserted in the core,
- a. The reactor mode switch is OPERABLE and locked in the Shutdown position or in the Refuel position per Table 1.2 and Specification 3.9.1.
- b. The source range monitors (SRM) at' OPERABLE per Specification 3.9.2.
- c. The SHUTOOWN MARGIN requirements of Specification 3.1.1 are satisfied, except that the contrel rod selected to be removed;
- 1. May be assumed to bc the highest worth control rod required to be assumed to be fully withdrawn by the SHUTDOWN MARGIN test, and
- 2. Need not be assumed to be imovable or untrippable,
- d. All other control rods in a five-by-five array centered on the control rod being removed are inserted and electrically or hydraulically disarmed or the four fuel assemblies surrounding the control rod or control rod drive mechanism to be removed from the core and/or reactor vessel are removed from the core cell.
- e. All other control rods are inserted.
APPLICABILITY: OPERATIONAL CONDITION 4 and 5. ACTION: With the requirements of the above specification not satisfied, suspend removal cf the control rod and/or associated control rod drive mechanism from the core and/or reactor pressure vessel and initiate action to s_atisfy the
~
ve requ}nments.MT!0tiAL C0tiDIT10ti change's per Specification 3.0.4 are
= ' s %_
dL $$-01 pm REFUELING OPERATIONS 3/4.9.11 RESIDUAL HEAT REMOVAL AND_ COOLANT CIRCULATION HIGH WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.11.1 At least one shutdown cooling mode train of the residual heat removal (RHR) systes shall be OPERAELE and in operation" with at least:
- a. One OPERABLE RHR pump, and
- b. One OPERABLF RHR heat exchanger train.
APPL 1tABILITY: OPERATIONAL CONDITION 5, when irradiated fuel is in the rea:ter vessel anc tne water level is greater than or equal to 22 feet 8 inches above the top of the reactor pressure vessel flange. ACTION:
- a. With no RHR chutdown cooling mode train OPERABLE, within one hour and at least once per 24 hours thereafter, demonstrate the OPERABIL1TY of at least one alternate method capable of decay heat removal. Otherwise, suspend all operations involving an increase in the reactor decay heat load and o' establish SECONDARY CONTAINMENT INTEGRITY within 4 hours.
- b. With no RHR shutdown cooling mode train in operation, within one hour establish reactor coolant circulation by an alternate method and monitor reactor coolant temperature at least once per hour, t N p:vhhn: Of l;;;i fice'.ier 0.0. 4 ei . in.1i. .pgih.. Liv.' l l
i l
$URVEILLANOE REQUIREMENTS
, l l 1 4.9.11.1 At least one shutdown cooling mode train of the residual heat remeval l [ system or alternate method shall be verified to be in operation and circulating reactor coolant at least once per 12 hours. l l r
\
1 .
. i l
The shutdown cooling pump may be removed from operation for up to 2 hours per l l 8 hour period. A N: ::::;the b :;;1 h:bh =t" :tutup f ra it; ;;;er,d re f e;16; ::t:;: cRAND cug uNn I w 1. uteentN=.$-Ii: i
Pld
* 'P4L BS-Ol REFUELING OPERATION 5'
(.~.. LOW WATER t.EVEL , LIMITING CONDITION FOR OPERATION Two shutdown cooling mode trains of the residual heat recovel IRHR) 3.9.11.2 system shall be OPERABLE and at least one train shall be in ooeration.* vith each train consisting of at least:
- a. One OPERABLE RHR pump, and
- b. One OPERABLE RHR heat exchanger train.
OPERATIONAL CONDITION 5, when irradiated fuelthe is in theofreactor top tne APPLICABILITY: vessel ano tne water level is less than 22 feet 8 inches abov?. reactor pressure vessel flange. ACTION:' a. With less than the above required shJtdo,tn cooling mode trains of the RHR system OPERABLE, within one hour and at least once per 24 hours therea demonstrate the OPERABILITY of at Itast one alternate method capable of decay heat removal for each inoperable RHR shutdown cooling mode train. mode train in opera' ion, within one hour
.( b. With no RHR shutdown coolin establish r6 actor coolant c rculation by an alternate method and monitor reactor coolant ter.perature at least once per hour,
- c. Th: pr:vi:f:n: Of $;;;ific;ti;a 3.0.4 er; act ;;;iic;tt;.#
i SURVE1LLANCE REQUIREMENTS At least one shutdown cooling mode train of the residual heat removal 4.9.11.2 system or alternate method stia11 be verified to be in operation and circu reactor coolant at least once per 12 hours. . i l l i l f* . \ . c
=
The shutdown cooling pump say be removed from operation for up to'2 ho per 8 hour period. M c: h:!' ; : te;'.- k - Thi; exce;ti;r i;-:;;!!! M e eat" st"t"* ":- t't -:::: Amendme't No. 38,- '- l 3/4 9 19 GRA'i: GU'.r UN:* 1
J ML ST-01 Pld , RADI0 ACTIVE EFFLUENTS f
.p DOSE -
LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or use commitment to a MENtER 0F THE PU8t!C from radioactive ! saterials in liquidii uents released, from oc h reactor unit, to UNRESTRICTED ! NtEAS (see Figure 5.) 9) shall be limited: !
- a. During any cabndar quarter to less than or equal to 1.5 mrem to the !
total body and to less than or equal to 5 area to any organ, and ,
- b. During any calendar year to less than or equal to 3 mres to the '
total body and to less than or equal to 10 mrem to any orgen. ; i: APPLICABILITY: At all times. l ACTION':
- a. With the calculated dose from the release of radioactive materials ,
! in liquid effluen+.s exceeding any of the above limits, prepare and l l submit to the Commission within 30 days, pursuant to Specifica- !
- tion 6.9.2, a Special Report which identifies the causa(s) for !
- . exceeding the limit (s) and defines the corrective actions that have f been taken to reduce the releases and the corrective actions to be L (s .
taken to ensure that future releases will be in compliance with the above limits. This Special Report shall also include (1) the results I of radiological analyses of the drinking water source and (2) the : l radiolcpical impact on finished drinkin
- to the requirements of 40 CFR Part 141 g water supplies with regard i r j b. The provisions of Specificatiok 3.0.3.ed4rer+ are not applicable.
l t F I SURVEILLANCE REQUIREMENTS i . . ,
- i l 4.11.1.2 Dose Calculations. Cumulative dose contributions from liquid effluents ;
4 for the current calendar quarter and the current calendar year shall be de'eemined f i in accordance with the methodology and parameters of the 00CM at least once l per 31 days. l i i l ' t < r
- l. "Appli7ble only if drinking water supply is taken from the receiving water I j' ,
.: body C. thin 3 miles downstream of the plant discharge. l l \~
! . i I GRAND GULF-UNIT 1 3/4 11-5 AmsweMax h. . !
._2 -
l _ _ , _ _ - _ _ - _ _ __.__.___________a
EITO WL M el RADI0 ACTIVE EFFLUENTS i
- j
.i LIQUID WASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.1.3 The liquid radwaste system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected do es due to the liquid effluent from each reactor unit to UNRESTRICTED AREAS (see Figure 5.1.3-1) would exceed 0.06 mrem to the total body or 0.2 area to any organ, in a 31-day period.
APPLICABILITY: At all times. ACTION:
- e. .
- With radioactive liquid waste being discharged without treatment
- and in excess of the above limits, prepare and submit to the Commis-sion, within 30 days pursuant to Specification 6.9.2, a Special Report which includes the following information:
- 1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoptrable equipment or subsystems, which resulted in liquid radwaste being discharged without treatment, and the reason for the inepersbility, and
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and ,
- 3. Summary description of action (s) taken to prevent a recurrence,
- b. TheprovisionsofSpecificationk3.0.3ud2.^.'arenotapplicable.
SURVEILLANCE REQUIREMENTS l 4.11.1.3.1 Doses due to liquid releases from each reactor unit to UNRESTRICTED AREAS shall be projected at least once per 31 days, in accordance with method- ! ology and parameters in the CDCM. 4.11.1.3.2 The installed liquid radwaste systen shall be demonstrated OPERABLE by meeting Specifications 3.11.1.1 and 2.11.1.2.
PISS ML SS-et RADI0 ACTIVE EFFlUiNTS
.b LIQUIDHOLOUPTANy -
LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in any out*'+ tempo- , rary tank, not including liners for shipping radwaste, shall be limi ..a to loss than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases. At all times, s APPLICABILITY: . ACTION-
- a. With the quantity of radioactive material in any of the above specified tanks exceeding the above limit, imroediately suspend all additions of radioactive material to the tanks and within 48 hours reduce the tank contents to within the limit, and describe the events leading to the condition in the next Semiannual Radioactive Effluent Release Report,
- b. TheprovisionsofSpecification\,,.0.3ed2.0.'arenot applicable.
( SURVEILLANCE REQUIREMENTS i 4.11.1.4 The quantity of radioactive material contained in each of the above specified tanks shall be determined to be within the above limit by analyzing a representatise sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank. t l ,.. l (.
~
l l CRAND GULF-UNIT 1 3/4 11-7 km.n tk. _ l
PD. . oh. 94 ol RADI0 ACTIVE EFFLUENTS DOSE - NOBLE GASES LIMITING CONDITION FOR OPERATION -- ,, 3.11.2.2 The air dose due to noble gases released in gaseous effluents, from each reactor unit, from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1.3-1) shall be limited to the followim During any calendar quarter: Less than or equal to 5 mrad for gamma ' a. radiation and less than or equal to 10 mrad for beta radiation, and During any calendar year: Less than or equal to 10 mrad for gamma b. radiation and less than or equal to 20 mrad for beta radiation. APPLICABILITY: At all times. ACTION:
- a. With the calculated air dose from the radioactive noble gases in gaseous eff'aents exceeding any of the above limits, prepare and -
submit to the Commission within 30 days, pursuant to Specifica-tion 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be . taken to ensure that future releases will be in compliance with Specification 3.11.2.2. The provisions of Specification \ 3.0.3 :nd 2.".' are not applicable. b. SURVEILLANCE REQUIREMENTS Cumulative dose contributions for noble gases 4.11.2.2 Dose Calculations.
- for the current calendar quarter and current calendar year shall be determined in accordance with the methodology and parameters in the 00CM at least once per 31 days.
I GRAND GULF-UNIT 1 3/4 11-12 kucwoksut 40. - t i
RADIOACTIVE EFFLUENTS DOSE - 10 DINE-131, 10 DINE-133, TRITIUM AND RADIONUCLIOES IN PARTICULATE FORM F( 4 LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium and radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1.3-1) shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 7.5 mres to any organ, and
- b. During any calendar year: Less than or equal to 15 mrem to any organ.
APPLICABILITY: At all times. ACTION:
- a. With the calculated dose from the release of iodine-131, fodine-133, tritium and radionuclides in particulate form, with half-lives greater than 8 days, in gaseous effluents exceeding any of the above j
( s limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce releases and the proposed corrective actions to be taken to ensure that future releases will be in compliance with
' Specification 3.11.2.3.
3.0.' are not applicable. ! b. The provisions of Specification \ 3.0.3-a SU_RVEILLANCE REQUIREMENTS 4.11.2.3 Dose Calculations. Cumulative dose contributions from iodine-131, iodine-133, tritium and racionuclides in particulate form with half-lives greater than 8 days for the current calendar quarter and current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days. ki', GRAND GVLF-UNIT 1 3/4 11-13 M .,eu rwr K . -
Pit't . NL SS-Gl RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT
. LIMITING CONDITION FOR OPERATION 3.11.2.4 The GASEOUS RADWASTE TREATMENT (0FFGAS) SYSTEM shall be in operation.
APPLICABILITY: Whenever the main condenser air ejector system is in operation. C A_C M:
- a. With gaseous radwaste from the main condenser air ejector system being discharged without treatment for more than 7 consecutive days, prepare and submit to the Commission within 30 days, pursuant ta Specification 6.9.2, a Special Report which includes the following information: ,
- 1. Explanation of why gaseous radwaste was being discharged without treatment, identification of the inoperable equipment
.', or subsystems which resulted in gaseous radwaste being discharged without treatment, and the reason for inoperability,
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and
- 3. Summary description of action (s) taken to prevent a recurrence.
- b. The provisions of Specification} 3.0.3-;r4 .^.' are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.4 The instruments specified in the ODCM shall be checked every 12 hours whenever the main condenser air ejector system is in operation to ensure that the GASECUS RADWASTC TREATMENT (OFFGAS) SYSTEM is functioning. 3/4 11-14 .Je 4 e. GRAND GULF-UNIT 1
PISS kt. h ot RADI0 ACTIVE EFFLUENTS
.I9 VENTILATION EXHAUST TREATMENT LIMITING CONDITION FOR OPERATION 3.11.2.5 The VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials In gaseous waste prior to their discharge when the projected dose due to gaseous effluent releases from each reactor unit to areas at and beyond the SITE BOUNDARY (see Figure 5.1.3-1) in a 31 day period would exceed 0.3 arem to any organ.
APPLICABILITY: At all times other than when the VENTILATION EXHAUST TREATMENT SYSTEM is undergoing routine maintenance." ACTION:
- a. With gaseous waste being discharged without treatment and in excess e
of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which , includes the following information: i
- 1. Explanation of why gaseous radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems which resulted in gaseous radwaste being discharged without treatment, and the reason for the inoperability,
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and
- 3. Summary description of action (s) taken to prevent a recurrence.
! b. The provisions of Specification \ 3.0.3 d 3.1 ' are not applicable.
I
- SURVEILLANCE REQUIREMENTS t
b . 4.11.2.5.1 Doses due to gaseous releases from each reactor unit to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodologj and parameters in the 00CM. 4.11.2.5.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE by meeting Specifications 3.11.2.1 and 3.11.2.2 or 3.11.2.3. j . [I "Not applicable to Turbine Building ventilation exhaust unless filtration - T. media is installed. l 7 T GRAND GULF-UNIT 1 3/4 11 15 W.- l 1 I
Pin NL ts ci RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.6 The concentraticri of hydrogen in the main condenser offgas treatment system shall be limited to less than or equal to 4% by volume. APPLICABILITY: Whenever the main condenser offgas treatment system is in operation. , ACTION:
- a. With the concentration of hydrogen in the main condenser offgas treatment system exceeding the limit, restore the concentration to within the limit within 48 hours.
- b. The provisions of Specification { 3.0.3 rd 2.0.' are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.6 The concentration of hydrogen in the main condenser offgas treatment system shall be determined to be within the above limits by monitoring the waste gas in the main condenser off gas treatment system with the hydrogen monitor OPERABLE as required by Table 3.3.7.12-1 of Specification 3.3.7.12.
+
GRAND GULF-UNIT 1 3/4 11-16 caomi R. -
pis, PJL SS-os RADIOACTIVE EFFLUENTS 3/4.11.3 SOLIO RADIOACTIVE ' WASTE LIMITING CONDITION FOR OPERATION 3.11.3 The solid radwaste system shall be used in accordance with a PROCESS CONTROL PROGRAM to process wet radioactive wastes to meet shipping and burial ground requirements. APPLICABILITY: At all times. ACTION:
- a. With the provisions of the PROCESS CONTROL PROGRAM not satisfied, suspend shipments of defectively processed or defectively packaged solid radioactive wastes from the site, b.f The provisions of Specification \ 3.0.3 ed 2.1' are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.3 The PROCESS CONTROL PROGRAM shall be used to verify the SOLIDIFICATION
- of at least one representative test specimen from at least every tenth batch of each type of wet radioactive waste.
- a. If any test speciment fails to verify SOLIDIFICATION *, the SOLI 0I-FICATION* of the batch under test shall be suspended until such time as additional test specimens can be obtained, alternative SOLIDIFI-CATION" parameters can be determined in accordance with the PROCESS CONTROL PROGRAM, and a subsequent test veriffes SOLIDIFICATION.*
SOLIDIFICATION
- of the batch may then be resumed using the alternative SOLIDIFICATION
- parameters determined by the PROCESS CONTROL PROGRAM.
- b. If the initial test specime7 from a batch of the waste fails to verify SOLIDIFICATION,* the PROCESS CONTROL PROGRAM shall provide for the collection and testing of representative test specimens from each consecutive batch of the same type of wet waste until at least 3 consecutive initial test specimens demonstrate SOLIDIFICATION.*
The PROCESS CONTROL PROGRAM shall be modified as required, as provided in Specification 6.13 to assure SOLIDIFICATION
- of subsequent batches of waste.
*Except dewatering.
' 3/4 11-18 N. GRAND GULF-UNIT 1 _ __-.---.-___-,,,.7
plS'S WL SS-01 RADI0 ACTIVE EFFLUENTS
.i 3/4.11.4 TOTAL DOSE .
LIMITING CONDITION FOR OPERATION _ 3.11.4 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC cue to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 arem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 arem. APPLICABILITY: At all times. l ACTION:
- a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents excteding twice the limits of Specifi-cations 3.11.1.2.a, 3.11.1.2.b. 3.11.2.2.a. 3.11.2.2.b 3.11.2.3.a, or 3.11.2.3 b, calculations should be made ine.luding direct radiation I contributions from the reactor units and from outside storage tanks to determine whether the above limits of Specification 3.11.4 have been exceeded. If such is the case, prepare and submit to the Commis-sion within 30 days, pursuant to Specification E.9.2, a Special Report
- that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits ar.d includes the schedule for achieving conformance with the above limits. ( This Specitl Report, as defined in 10 CFR Part 20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceeds the above limits, and if the release condition result-ing in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a reauest for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.
- b. The provisions of Specification \ 3.0.3 cd 11' are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the methodology and parameters in the 00CH. 4.11.4.2 Cumulative dose contributions from direct radiation from the reactor units and from radwaste storage tanks shall be determined in accordance with (' the methodology and parameters in the 00CM. This requirement is applicable only under conditions set forth in Specification 3.11.4.a. GRAND GULF-UNIT 1 3/4 11-19 b swo* M
3/4.12 ItADIOLOG! CAL ENV?RONMENTAL MONITORINO 3/4.12.1 MONITORIN PROGRAM
, LIMITING CONDITION FOR OPERATION (2' .1
, , 3.12.1 The radiological environmental sonitoring program shall be conducted as specified in Table 3.12.1-1. APPLICA81LITY: At all times.
~
ACTION: l *
- a. With the radiological environmental monitoring program not being conducted as specified in Table 3.12.11, prepare and subett to the Cosseission, in the Annual Radiological Environmental Operating
, Report per Specification 6.9.1.7, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence. i b. With the level of radioactivity as the result cf plant effluent in ! an environmental sampling medium at a specified location exceeding , the reporting levels of Table 3.12.1-2 when averaged over any calendar l quarter, prepare and submit to the Comission within 30 days pursuant j to Specification 6.9.2 a Special Report that identifies the cause(s) i for exceeding the limit (s) and defines the corrective actions to be i taken to reduce radioactive effluents so that the potential annual dose to a MEM3ER OF THE PUBLIC is Ir..s than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3. When more than one of the radionuclides in Tabir. 3.12.12 are detected in the sampling medium, this report sna11 be submittec if: concentration (1) .0 reporting level (1)
- concentration (2) reporting level (2) + .. 1 When radionuclides other than those in Table 3.12.1 2 are detected and are the result of plant affluents, this report shall be submitted if the potential annual dose to a MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of Specificatiet.s J.11.1.2, 3.11.2.2 and 3.11.2.3. This nport is not requirvd if the seasured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report, e If milk or broad leaf vegetation sampling is relocated fron one or i more of the sample locations required by Table 3.12.1-1, identify I
new locations for obtaining replacement samples and add them to the ( radiological environmental sonitoring program within 30 days. In I addition, report the cause(s) of the unavailability of samples and the new locations for obtaining m placement samples in the next Semi-annual Radioactive Effluent Release Report. Include in this report the revised 00CM figure (s) and table (s) Mflecting the new locations. The specific locations free which samples were unavailable say then be deleted froe the radiological environmental sonitoring program and the table (s) in the CDCM, provided the locations from which the replace-ment samples were obtained are added to the table (s) as replacement locations,
- d. The provisions of Specification \ 3.0.3-=d L^ ' ate not applicable.
( GRM C GULF-UNIT 1 3/4 12-1 Amendnnt No. 21, _
. __- _,_.__._.__,,-..,_----,-,.,7
A vir o P 1(,0 i RADIOLOGICAL ENVIRONMENTAL MONITORING
,; 3/4.12.2 LAND USE CEN5us LIMITING CONDITION FOR OPERATION ,
3.12.2 ! A lano use census shall be conducted and shall identify within a distance of 8 kn. (5 miles) the location in each of the 16 seteorological sectors of the ne0 rest milk animal, the nearest residence and the nearest garden of greater .'han 50 m2 (500 f t2) producing broad leaf vegetation. Broad be performed at the SITE BOUNDARY in each of two diff i with the highest predicted D/Qs in lieu of the garden census. Specifications i for broad analysis including leaf vegetation sampling of control samples. in Table 3.12.1-1 shall be followed, , APPLICABILITY: At all times. ACTION: a. With a land use census identifying a location (s) which yields a calculated dose or dose commitment greater than the values currently
- being calculated in Specification 4.11.2.3, identify the new locationpursuant Report, (s) in theto next Semiannual Specification Radioactive Effluent Release 6.9.1.9.
b. With a land use census identifying a location (s) which yields a C. calculated dose or dose commitment (via the same exposure pathway)
- 20 percent greater than at a location from which samples are i 1 currently bdng obtained in accordance with Specification 3.12.1, add 3 the new withia program location 30 (s) to the radiological environmental monitoring days. The sampling location (s), excluding the control station location, having the lowest calculated dose or dose (
commitment (s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this { land use census was conducted. Identify the new location (s) in the next Semiannual Radioactive Effluent Release Report and also ' include in the report a revised figure (s) and table (s) for the ODCM reflecting the new location (s). , c. The provisions of Specificationk 3.0.3 n: 2.0. t are not applicable. : l SURVEILLANCE REQUIREMENTS 4.12.2 The land use census shall be conducted during the growing season at least once per 12 months using that information that will provide the best ; i results, such as by local agriculture a door-to-door survey, aerial survey, or by consulting authorities. < The results of the land use census shall be included in the6.9.1.7. Specification Annual Radiological Environmental Operating Report pursuant to k f y w GRAND GULF-UNIT 1 3/4 12-11 bow 4. Aw+
RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARIS0N PROGRAM LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on radioactive materials that correspond to samplen required by Table 3.12.1-1. These materials are supplied as part of an Interlaboratory Comparison Program which has been approved by the Commission. APPLICABILITY: At all times. ACITON:
- 0. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annus1 Radiological Environmental Operating Report pursuant f to Specification 6.9.1.7.
b. TheprovisionsofSpecification\(3.0.3.nd2.0.0arenotappilcable. SURVEILLANCE REQUIREMENTS l 4.12.3 A summary of the results obtained as part of the above required { Interlaboratory Comparison Program shall be included in the Annual Radiological l Environmental Operating Report pursuant to Specification 6.9.1.7. l l l l l m GRAND GULF-UNIT 1 3/4 12 12 gg g, _ s_ -
. - ~ . .
pl(o1 NL M k, h /4.0 APPLICABILITY BAS j The applicable ecifications of this section provide the general requirements o each of the Limiting Conditions for Operation and Surveil Requiremerits within Section 3/4. nee
- 3. 0.1 Thi specification states the applicability of each sp ification in terms ofand condition definisdpOPERATIONAL CONDITION or other specified appi cability applicable. vided to delineate specifically when each s cification is 3.0.2 1.r.s specif ation defines those conditions ne essary to constitute compliance with the terms of an individual Limiting Cond ion for Operation and associated ACTION requ ement.
3.0.3 This specificatio delineates the measu s to be taken for those circumstances not directly prov ed for in the ACT N statements and whose occurrence would violate the int t of the speci cation. For example, Specifiestion 3.7.2 requires two e ntrol room ergency filtration subsystems C to be OPERABLE and provides explici ACTION r uirements if one subsystem is inoperable. Under the requirements o Speci ication 3.0.3, if both of the required subsystems are inoperable, wi to place the unit in at least STARTUP wt in in ne hour measures must be initiated the next 6 hours, in at least HOT SHUTDOWN within the following 6 hours a subsequent 24 hours. As a further exar e, in atecification least COLD SHUT 00WN within the 3.6.7.1 requires two primary containment hydrogen recombi r syst s to be OPERABLE and provides explicit ACTION requirements if on recombine system is inoperable. Under the requirements of Specification .0.3, if bot of the required systems are inoperable, within one hour sea res must be ini ated to place the unit in at least STARTUP within the next following 6 hours, hours and in at le st HOT SHUTOOWN within the 3.0.4 This specific ion provides that entry into n OPERATIONAL CONDITION must be made th (a) the full complement of r utred systems, equipment or component OPERABLE and (b) all other paramet rs as specified in the Limiting Conditi s for Operation being met without reg d for allowable deviations and out i service provisions contained in the AC ON statements. . The intent f this provision is to ensure that unit operati n is not initiated with ither required equipment or systems inoperable or ther limits being exceede . Excep ions to this provision have been provided for a limited n , er v specific . ions when startup with inoperable equipment would not affect S safety. These exceptions are stated in the ACTION statements of the . ( appro iate specifications. AND GULF-UNIT 1 8 3/4 0-1
Dlfo3 Kn. M m WPLICABILITY BA /
~
4.0. This specification provides that surveillance activities nece ary to ensure e Limiting Conditions for Operation are met and will be perf med during the O RATIONAL CONDITIONS or other conditions for which the Li ting Conditions fo Operation are applicable. Provisions for additional s veillance activities to b performed without regard to the applicable OPERATIO AL CONDI-TIONS or other co itions are provided in the individual Surveilla e Requirements. Sur illance Requirements for Special Test Exceptians ne.J only an aception be performed when th Special Test Exception is being utilized to an individual spec ication. 4.0.2 The provision of this specification provide al wable tolerances for performing surveillance etivities beyond those specif ed in the nominal surveillance interval. Thes tolerances are necessary t provide operational flexibility because of schedul g and performance consi erations. The phrase "at least" associated with a sur eillance frequency d s not negate this allowable tolerance; instead, it rmits the more fr quent performance of surveillance activities. The tolerance values, taken eithe individ 11y or consecutively over 3 test intervals, are sufficiently restr tive o ensure that the reliability associated with the surveillance activity 's et significantly degraded beyond that obtained from the nominal specified in rval. 4.0.3 The provisions of this speci catio set forth the criteria for determination of compliance with the OP ABILITY equirements of the Limiting Conditions for Operation. Under this riteria, eq ipment, systems or components are assumed to be OPERABLE if the as ciated survei ance activities have been Nothing in this satisfactorily performed within th specified time in rval. provision is to be construed as d ining equipment, sys ms or components OPERABLE, when such items are fe nd or known to be inope ble although still meeting the Surveillance Requir ments. 4.0.4 This specificati n ensures that surveillance acti ties associated with a Limiting Conditions or Operation have been performed vi in the specified time interval prior to e ry into an applicable OPERATIONAL COND ION or other specified applicability endition. The intent of this provision i to ensure that surveillance acti ties have been satisfactorily demonstrated o a current basis as required to eet the OPERABILITY requirements of the Limitin Condition for Operation. Under the t ms of this specification, for example, during initial pla t startup or foil wing extended plant outage, the applicable surveillance acti ities must be erformed within the stated surveillance interval prior to placi or, returning he system or equipment into OPERABLE status. AND GULF UNIT 1 B 3/4 0 2
.___ _ _ _ =
ht. 19-el PO NPPLICABILITY BA
/
4.0.5 is specification ensures that inservice inspection of ASME de Class 1, 2 and components and inservice testing of ASME Code Class 1, and 3 pumps and valve will be performed in accordance with a periodically pdated version of Section of the ASME Boiler and Pressure Vessel Code and ddenda as required by 10 CFR , Section 50.55a. Relief from any of the ab ve require-ments has been provided writing by the Commission and is not a rt of these Technical Specifications. This specification include a clarification of the freque ies of perform-ing the inservice inspection and sting activities required y Section XI of the ASME Boiler and Pressure Vessel de and applicable Add da. This clarifi-cation is provided to ensure consisten > in surveillance i tervals throughout these Technical Specifications and to re ve any ambigui .es relative to the frequencies for performing the required ins vice inspe ion and testing activ-ities. < l Under the terms of this specification, the mo restrictive requirements of the Technical Specifications take precedence o r e ASME Boller and Pressure Vessel Code and applicable Addenda. For example the uirements of Specifi-cation 4.0.4 to perform surveillance activitie prior to try into an OPERATIONAL CONDITION or other specified applicability ce dition takes cedence over the ASME Boiler and Pressure Vessel Code provis n which allows pu. s to be tested (" up to one week after return to normal oper ion. And for exampi the Technical Specification definition of OPERABLE doe not grant a grace period fore a device that is not capable of performin its specified function is de ared inoperable and takes precedence over e ASME Boiler and Pressure Vesse rovi-sion which allows a valve to be inca ble of performing its specified func on for up to 24 hours before being dec ared inoperable. i j I t 1 ( l AND GULF-UNIT 1 B 3/4 0-3
PIW NL.%5-ot 3/4.0 APPLICABILITY 8ASES Specifications 3.0.1 through 3.0.4 establish the general requirements applicable to Limiting conditions for Operation. These requirements are based on the requirements for Limiting (Conditions for Operation stated in the Cod Regulations,10CFR50.36c)(2):
"Limiting conditions for operation are the lowest functional capability or perforn nce levels of equipment required for safe operation of the facility. When a limiting cendition for operation of a nuclear reactor is net
- met, the licensee shall shut down the reactor or follow any remedial action pemitted by the technical specification until the condition can be met."
5pecification 3.0.1_ establishes the Applicability statement within each individual specification as the requirement for when i.e., in which OPERATIONAL CONDITIONS or other specified conditions)(conform , Limiting Conditions for Operation is required for safe operation of the facility. The ACTION requirements establish those remedial measures that must be taken within specified time limits when the requirements of a Limiting Condition for Operation are not met. It is not intended that the shutdown ACTION requirements be used as an operational convenience which permits (routine) voluntary removal of a system (s) or comfonent(s) from service in lieu of other alternatives that would not result in redundant systems or components being inoperable. I There are two basic types of ACTION requirements. The first specifies the remedial measures that pemit continued operation of the facility which is not further restricted by tie time limits of the ACTION requirements. In this case, conformance to the ACTION requirements provides an acceptable level of safety for unlimited continued operation as long as the ACTION requirements continue to be met. The second type of ACTION requirenent specifies a time l limit in which confomance to the conditions of the Limiting Condition for ! Operation must be met. This time limit is the allowable outage time to ; restore an inoperable system or component to OPERABLE status or for restoring parameters within specified limits. If these actions are not completed within the allowable outage time limits, a shutdown is required to place the facility in an OPERATIONAL CONDITION or other specified condition in which the , specification no longer applies, The specified time limits of the ACTION requirements are applicable from the point in time it is identified that a Liniting Cendition for Operation is not ret. The time limits of the ACTION requirements are also applicable when a system or component is removed from service for surveillance testing of-investigation of operational problems. Individual specifications may include a specified time lirit for the corrpletion of a Surveillance Requirerent when . B 3/4 0-1 ha,wr 9.. I GRAND GULF-UNIT 1
Plu N L 8001 3/4.0 APPLICARILITY , BASES (Con't) equipment is removed from service. In this case, the allowable outage time limits of the ACTION requirements are applicable when this limit expires if the surveillance has not been completed. When a shutdown is required to comply with ACTION requirements, the plant may have entered an OPERATIONAL CONDITION in which a new specification becomes applicable. In this casa, the time limits of the ACTION recuirements would apply from the point in time that the new specification becomes applicable if the requirements of the Limiting Condition for Operation are not met. S)ecification 3.0.2 establishes that noncompliance with a specifica' tion exists w1en the requirerents of the Limiting Condition for Operation are not met and the associated ACTION requirements have not been implemented within the specified time interval. The purpose of this specification is to clarify that (1) implementation of the ACTION requirenents within the specified time interval constitutes compliance with a specification and (2) coepletion of the remedial measures of the ACTION requirements is not reovired when compliance with a Limiting Condition of Operation is restored within the time interval specified in the associated ACTION requirements. nij@ Specification 3.0.3 establishes the shutdown ACTION requirements that must be implemented when a Limiting Condition for Operatio is not met and the condition is not specifically addressed by the ass ciated ACTION requirements. The purpose of this specification is to delineate he time limits for placing the unit in a safe shutdown CONDITION when plant peration cannot be maintained within the limits for safe operation 6 tned by the Limiting Conditions for Operation and its ACTION require nts. It is not intended to be used as an operational convenience which pe its (routine) voluntary removal of redundant systems or coeponents from servic in lieu of other alternatives that would not result in redundant systems or n ;: M: being inoperable. One hour is allowed to prepare for an orderly shutdown before initiating a change in plant operation. This time pemits the operator to coordinate the reduction in electrical generation with the load dispatcher to ensure the stability and availability of the electrical grid. The time limits specified to reach lower CONDITIONS of operation pemit the shutdown to oroceed in a controlled and orderly manner that is well within the specified maximum cooldown rate and within the cooldown capsM11 ties of the facility assuming only the minirum required equipment is OPERABLE. This reduces themal stresses on components of the primary coolant system and the potential for a plant upset that could challenge safety systems under conditions for which this specification applies. If remedial measures pemitting limited continued operation of the facility under the provisions of the ACTION requirements are completed, the shutdown may be teminated. The time limits of the ACTION requirements are applicable from the point in time nthere was a failure to meet a Limiting Condition for Operation. Therefore, the shutdown may be teminated if the ACTION requirements have been met or the time limits of the ACTION requirements have not expired, thus provi ding an allowance for the completion of the required i identified) GRAND GULF UNIT 1 B 3/4 0-2 bme L m
p@1 NL 61 ci 3/4.0 APPLICABILITY BASES (Con't) The tirne limits of Specification.3.0.3 allow 37 hours for the plant to be in COLD SHUTDOWN when a shutdown is required during POWER operation. If the plant is in a lower CONDITION of operation when a shutdown is required, the time limit for reaching the next lower CONMTION of operation applies. However, if a lower CONDITION of operation is reached in less time than allowed, the total allowable time to reach COLD SHUTDOWN, or other OPERATIONAL CONDITION, is not reduced. For example, if STARTUP is reached in 2 hours, the time allowed to reach HOT SHUTDOWN is the next 11 hours because the total time to reach HOT SHUTDOWN is not reduced from the allowable limit of 13 hours. Therefore, if remedial measures are completed that would pemit a return to POWER operation, a penalty is not incurred by having to reach a lower CONDITION of operation in lestthan the total titre allowed. (ii~ seconal _spcond -- The same principle a lies ~with regard to the allow IONrequirementsfor4a+.j_ le%tage time limits of the ACTION requir nts, if compliance with the A specification res ts in entry into an OPERATION . CONDITION or condition of operation for r.h- specification in which th recuirements specification becomes of the Limiting Condition for Operation are not met. If the applicable in less time than Uifid, the differene may be added to the a110w&bl6 ot.tage time limits /r e/ he t second specificat, .n,.u.u. tr/: e.n uthn m n e . <_
. % .u . ........ *,.. u.4., i m nu .....< - .,
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i l erM iceM e e e Li itir; leaditi- <e- Op- etfea 4 bet--t4- e be-C^'DITIO' Of "p^-etteN - INSERT [ i The shutdown requirements of Specification 3.0.3 do not apply in CONDITIONS 4 and 5, because the ACTION reoutrements of individual specifications define the
- remedial measures to be taken.
l Specification 3.0.4 establishes limitations on a change in OPERATIONAL CONDITIONS when a Limiting Condition for Operation is not met. It precludes l placing the facility in a higher CONDITION of operation when the requirements for a Limiting Condition for Operation are not met and continued noncompliance i I to these conditions would result in a shutdown to comply with the ACTION requirements if a change in CONDITIONS were permitted. The purpose of this l specification is to ensure that facility operation is not initiated or that higher CONDITIONS of operation are not entered when corrective action is being l taken to obtain coepliance with a specification by restoring equipment to l ' OPERABLE status or parameters to specified limits. Compliance with ACTION requirements that permit continued operation of the facility for an unlimited period of time provides an acceptable level of safety for continued operation without regard to the status of the plant before or after a change in OPEP.ATIONAL CONDITIONS. Therefore, in this case, entry into an OPERATIONAL CONDITION or other specified condition may be made in accordance with the provisions of the ACTION requirements. The provisions of this specification should not, however, be interpreted as endorsing the failure to exerciss-Sood I practice in restoring systems or components to OPEP>sBLE status before plant startup. B 3/4 0-3 ta e r t b. GRAND GULF-UNIT 1 l
, #L1s.ei pig 1 INSERT 1 was, required by the initial CTION requirements i l
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between the actual and the required time to reach the appitcability of the second specification I t i 1 i i 1 1 1 l ) l 4 1
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l 1 t I i 1 i J16 MISC 88080201 - 1 {
PIM 4 I NL Stool d 3/4.0 APPLICABILITY BASES (Con't)
- When a shutdown is required to comply with ACTION requirements, the provisions of Specification 3.0.4 do not apply because they would delay placing the facility in a lower CONDITION of operation. .
Specifications 4.0.1 through 4.0.5 establish the general requirements applicable to surveillance Requirements. These requirements are based on the surveillance Recuirements stated in the Code of Federal Regulations. l 10CFR50.36(c)(3): s I ' Surveillance requirements are requirements relating to test, calibration, or inspection to ensure that the necessary quality of systems and components is maintained, that facility operation vill be within safety limits, and that the limiting conditions of operation will be met.'
- Specification 4.0.1 establishes the requirement that surveillances must be i performed during the OPERATIONAL CONDITIONS or other conditions for which the
- requirements of the Limiting Conditions for Operation apply unless otherwise i stated in an individual Surveillance Requirement. The purpose of this specification is to ensure that surveillances are performed to verify the
! operational status of systems and components and that parameters are within l specified limits to ensure safe operation of the facility when the plant is in j en OPERATIONAL CONDITION or other specified condition for which the individual i Limiting Conditions for Operation are applicable. Surveillance Requirements do not hava to be performed when the facility is in an OPERATIONAL CONDITION [ for which the requirements of the associated Limidng Condition for Operation [ do not apply unless otherwise specified. The Surveillance Reoutrements associated with a Special Test Exception are only applicable when the Special l Test Exception f s used as an allowable exception to the requirements of a specification. l I Specification 4.0.2 establishes the conditions under which the specified time I Interval for Surveillance Recuirements may be extended. Item 4. permits an ! allowable extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g., transient conditions or other ongoing surveillance or maintenance activities. Item b. limits the use of the previsions of item a to ensure that it is not used repeatedly to extend the surveillance interval beyond that specified. The l limits of Specification 4.0.2 are based on engineering judynent and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirements. These provisions are sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval. . Specification 4.0.3 establishes the failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, as a condition that constitutes a failure GRAND GULF-UNIT 1 6 3/4 0-4 h we.a g.
Nt 53-01 pno 3/4.0 APPLICABILITY BASES (Con't) to meet the OPERABILITY recuirements for a Limiting Condition for Operation. Under the provisions of this specification, systees and components are assumed to be OPERABLE when Surveillance Requirements have been satisfactorily perfomed within the specified time interval. However, nothing in this arovision is to be construed as implying that systems or components are OPERAB.E when they are found or known to be inoperable although still meeting the Survet11ance Requirements. This specification also clarifies that the ACTION requirements are applicable when Surveillance Recuirements have not been completed within the allowed surveillance interval and that the time limits of the ACTION requirements apply from the point in time it is identified that a surveillance has not been perfomed and net at the time that the allowed surveillance interval was exceeded. Completion of the Surveillance Requirement within the allowable outage time limits of the ACTION requirements restores coep11ance with the requirements of Specification 4.0.3. However, this does not negate the fact that the failure to have perfomed the surveillance within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, was a violation of the OPERABILITY requirements of a Limiting Condition for Operation that is subject to enforcement action. Further, the failure to perfom a surveillance within the provisions of Specification 4.0.2 is a violation of a Technical Specification requirement and is, therefore, a reportable event under the requirements of 10 CFR 50.73(a)(2)(1)(B) because it is a condition prohibited by the plant's Technical Specifications. If the allowable outage time limits of the ACTION *equirements are less than 24 hours or a shutdown is required to comply with 3CTION requirements, e.g., Specification 3.0.3., a 24 hour allowance is provided to pemit a delay in implementing the ACTION requirements. This provides an adequate time Ifmit to coeplete Surveillance Requirenents that have not been perfomed. The purpose of this allowance is to pemit the completion of a surveillance before a shutdown would be required to comply with ACTION requirements or before other remedial measures would be required that may preclude the completion of a surveillance. The basis for this allowance includes consideration for plant conditions, adequate planning, availability of personnel, the time required to perfom the surveillance, and the safety significance of the delay in completing the required surveillance. This provision also provides a tire limit for the completion of Surveillance Requirements that become applicable as a consequence of CONDITION changes imposed by ACTION requirements and for completing Surveillance Requirements that are applicable when an exception to the requirements of 5)ecification < 4.0.4 is allowed. If a surveillance is not completed within tie 24-hour allowance, the time limits of the ACTION rtquirements are applicable at that time. When a surveillance is perforred within the 24-hour allowance and the Surveillance Requirements are not met, the time limits of the ACTION requirements are applicable at the time that the surveillance is teminated. Surveillance Requirements do not have to be perfomed on inoperable equipment because the ACTION requirecents define the reredial ressures that apply. " However, the Surveillance Requirements have to be met to demonstrate that inoperable equipment has been restored to OPEPABLE status. GRAND GULF-UNIT 1 B 3/4 0-5 Aroemo Na _ _ _ _ _ _ _ __j
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, tJL $$-ol 3/4.0 APPLICABILITY BASES (Con't)
Specification 4.0.4 establishes the requirement that all applicable surveillances muWbe met before entry into an OPEPATIONAL CONDITION or other condition of operation specified in the Applicability statement. The purpose of this specification ja to ensure that system and component OPERABILITY requirements or parameter limits are met before entry into an OPERATIONAL CONDITION or other specified condition for which these systems and components ensure safe operation of the facility. This provision applies to changes in OPERATIOML CONDITIONS or other specified conditions associated with plant shutdown as well as startup. Under the provisions of this specification, the applicable Surveillance Requirements must be performed within the specified surveillance interval to assume that the Limiting Conditions for Operation are met during initial plant startup or following a plant outage. When a shutdown is required to comply with ACTION requirements, the provisions of Specification 4.0.4 do not apply because this would delay placing the facility in a lower CONDITION of operation.
- Specification 4.0.5 establishes the requirement that inservice inspection of X5ME code Class 1, 2, and 3 componer.ts and inservice testing of ASME Code Class 1, 2. and 3 pumps and valves shall be performed in accordance with a i periodically updated version of Section XI of the ASME Roller and Pressure J Yessel Code and Addenda as required by 10 CFR 50.55a. These requirements
( apply except when relief has been provided in writing by.the Ccrnmission. l This specification includes a clarification of the frequencies for perfoming i the inservice inspection and testing activitics required by Section XI of the ASME Boiler and Pressure Yessel Code and applicable Addenda. This clarification is provided to ensure consistency in surveillece intervals throughout the Technical Specificatiens and to remove any ambiguities relative " i to the frequencies for perfoming the required inservice inspection and , testing activities. I linder the terms of this specificatien, the more restrictive requirements of l the Technical Specifications take precedence over the ASME Boiler and Pressure Yessel Code and applicable Addenda. The requirements of Specification 4.0.4 to perfom surveillance activities before entry into an OPEPATIONAL CONDITION or other specified condition takes precedence over the ASME Boiler and Pressure Vessel Code provision that allows pumps M d = to be tested up to one week after return to normal operation. The Technical Specification definition of OPERABLE does not allow a grace period before a component, which is not capable of perfoming its specified function is declared inoperable - and takes precedence over the ASME Boiler and Pressure Vessel Code provision that allows a valve to be incapable of performing its specified function for up to 24 hourt before being declared inoperable. GRAND GULF-UNIT 1 B 3/4 0-6 bro.uu N. i}}