ML20216E479

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Proposed Tech Specs Revising Allowable Values for CST Low Water Level Limits from Greater than or Equal to 59,700 Gallons to Greater than or Equal to 90,300 Gallons
ML20216E479
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 09/09/1999
From:
CENTERIOR ENERGY
To:
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ML20216E475 List:
References
NUDOCS 9909140079
Download: ML20216E479 (28)
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ECCS Instrumentatien 3.3.5.1 Attachment 3 PY-CEl/NRR-2430L ACTIONS (continued) Page 1 of14 CONDITION REQUIRED ACTION COMPLETION TIME E. As required by E.1 --------NOTES----- ;- 4 Required Action A.1 1. Only applicabl j and referenced in MODES 1, 2, and .

Table 3.3.5.1-1. 3. -

2. Only applicable for Functions 1.f, 1.g, and 2.e.

______________.._____ 2 Declare supported I hour from feature (s) inoperable discovery of when its redundant loss of feature ECCS initiation initiation capability capability for is inoperable. feature (s) in both divisions M '

E.2 Restore channel to 7 days OPERABLE status.

(' ) ~

F. As required by Required Action A.1 F.1 Declare Automatic 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from Depressurization discovery of and referenced in System (ADS) valves loss of ADS Table 3.3.5.1-1. . inoperable. initiation'.

capability'in M

both trip )

systems '

F.2 Place channel in 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> from trip. discovery of inoperable

' channel concurrent with HPCS or reactor core isolation cooling (RCIC) inoperable M

8 days (continued)

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PERRY - UNIT 1 3.3-36 Amendment No. 69 9909140079 990909 PDR ADOCK 05000440 P PDR

ECCS Instrumentation 3.3.5.1 Attachment 3 Table 3.3.5.1 1 (page 3 of 5)

Emergency Core tooting System Instrumentation PY-CEl/NRR-2430L Page 2 of14 APPLICABLE CONDITIONS MODES OR REFERENCED OTHER RE0LilAED FRON .

SPECIFIED CHANNELS PER REQUIRED FUNCTION SURVE!LLANCE CONDITIONS FUNCTION ALLOW 4BLE ACTION A.1 REQUIREENTS var sg

2. LPCI B and LPCI C

$4 systems (continued)

e. LPCI Puup B 1,2,3, 1 per pump E SR 3.3.5.1.1 and LPCI Puup C e 1450 sps

. Discharge 4(a) 5(*) SR 3.3.5.1.2 Flow- Low SR 3.3.5.1.3 (gypass) SR 3.3.5.1.5 SR 3.3.5.1.6

f. N. nuel Initiation
3. High Pressure Core sprey (NPCS) System
e. Reactor vesset 1,2,3, 4(*) B SR 3.3.5.1.1 Weter Level-Low k 127.6 Inebs Low, Level 2 4(*),5(e) SR 3.3.5.1.2 l SR 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6
b. Drywell 1,2,3 4(*) B SR 3.3.5.1.1 Pressure - High s 1.88 psig SR 3.3.5.1.2 l

,,'\ SR 3.3.5.1.3

! SR 3.3.5.1.5 SR 3.3.5.1.6

c. Reactor vesset 1,2,3, 4 3 Water SR 3.3.5.'1.1 s 221.7 inches Levet - Nigh, 4(*),5(*) SR 3.3.5.1.2 ,

Level 8 SR 3.3.5.1.3  !

SR 3.3.5.1.5 g g3oo SR 3.3.5.1.6

d. Cordensate 1,2,3, 2- D Storage Tank SR 3.3.5.1.1 settons Levet - Low 4(c) $(c) SR 3.3.5.1.2 -

SR^3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6

e. S e ston Poot 1,2,3 2 0 Water Level-Nigh SR 3.3.5.1.1 SR 3.3.5.1.2 s18ftIinches Sd 3.3.5.1.3 SR 3.3.5.1.5 SR 3.3.5.1.6 (continued)

(a) When associated essyst' em(s) are required to be OPERABLE.

(c) When NPCS 19 OPERABLE for compliance with LCO 3.5.2, "ECCS-Shutdown," and aligned to the condsnsate l

storage tank dite tank unter tevel is not within the timite of SR 3.5.2.2.

(e) Also required to initlete the associated dieset generator.

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PERRY - UNIT 1 3.3-41 Amendment No. 85

1 RCIC System Instrumentation 3.3.5.2 l Attachment 3 Table 3.3.5.21 (pose 1 of 1) PY-CE!/NRR-2430L I Reactor core Isolation Cooline system Instrumentation Page 3 of 14 l

. . . i CONDITIONS -

REQUIRED REFERENCED .

CHANNELS PER FROM REQUIRED SURVEILLANCE ALLOWABLE FUNCTION FUNCTION ACTION A.1 REQUIREMENTS VALUE l

1. Reactor vessel Water 4 Level-Low Low, Level 2 s st 3.3.5.2.1 1 127.6 inches st 3.3.5.2.2 st 3.3.5.2.3 st 3.3.5.2.4 SR 3.3.5.2.5
2. Reactor vessel Water 4 C SR 3.3.5.2.1 Level- High, Level 8 s 221.7 inches st 3.3.5.2.2 SR 3.3.5.2.3 st 3.3.5.2.4 SR 3.3.5.2.5 f 9dd'
3. Condensate storage Tank 2 D SR 3.3.5.2.1 ottons Level - Low st 3.3.5.2.2 st 3.3.5.2.3 SR 3.3.5.2.4 SR 3.3.5.2.5 4 Suppression Pool Water 2 0 Levet - High SR 3.3.5.2.1 s 18 ft 6 inches st 3.3.5.2.2 st 3.3.5.2.3 sa 3.3.5.2.4 st 3.3.5.2.5
5. Manuel Initiation 1 C SR 3.3.5.2.5 NA 4.

)

/ PERRY - UNIT 1 3.3-47 Amendment No. 69

, . . . l Primary Containment and Drywell Isolation Instrumentat 3.3.6.1 {

Attachment 3 Table 3.3.6.1 1 (page 6 of 6) '

1 Prienry Conts'nnent and Dryuell Isolation InstroentationPY-CEl/NRR-2430L Paoe 4 of 14 APPLICABLE CONDITits MODES OR REFERENGB '

OTHER REQUIRED FROM SPECIFIED CHANNELS PER REQUIRht FUNCTION CONDITIONS SURVEILLANCE TRIP SYSTEM ACTION C.1 ALLOWAstr REQUIREMENT,5 VALUE

3. RCIC System Isolation (continuar/)

5 Main Steam Line Pipe 1,2,3 1 Tunnel Temperature F SR 3.3.6.1.6 s 30 minutes Timer SR 3.3.6.1.5

h. RHR Equipment Area SR 3.3.6.1.7 1,2,3 1 per area F Anblent SR 3.3.6.1.1 s 159.9'F Temperature-Nish SR 3.3.6.1.6 SR 3.3.6.1.5 ER 3.3.6.1.7
1. RCIC team Line 1,2,3 1 F tou- gh F SR 3.3.6.1.1 s 55.6 SR 3.3.6.1.2 laches uster SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.5 J. Dryuei1 Pressure-Nigh 1,2,3 1 F SR 3.3.6.1.1 s 1.88 psig SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.5
k. Manuet Initiation 1,2,3 1 G SR 3.3.6.1.5 NA
  • - 4. Reactor Water Clear g (RWCU) System Isolation
a. Differential Flou-Nish 1,2,3 1 F SR 3.3.6.1.1 1 s 77.1 spa SR 3.3.6.1.2 St J.3.6.1.6 SR 3.3.6.1.5
b. Differentist 1,2,3 1 F Flow- Timer SR 3.3.6.1.2 s 10.85 SR 3.3.6.1.6 minutes SR 3.3.6.1.5
c. RWCU Neat Exchanger 1,2,3 ~ 1 Room Temperature-Eigh F SR 3,3.6.1.1 s 138.9'F SR 3.3.6.1.6

.! SR 3.3.6.1.5 SR 3.3.6.1.7 (continued) c..~.,

PERRY - UNIT 1 3.3-57 Amendment No. 59,79 l

l

ECCS-Operating

. 3.5.1 Attachment 3 PY-CEl/NRR-2430L SURVEILLANCE REQUIREMENTS Paae 5 of 14 SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify, for each ECCS injection / spray 31 days '.

subsystem, the piping is filled with water from the pump discharge valve to the injection valve.

SR 3.5.1.2 --_----------------NOTE--------------------

Low pressure coolant injection (LPCI) subsystems may be considered OPERABLE

. during alignment and operation for decay

) heat removal with reactor steam dome pressure less than the residual heat I removal cut in permissive pressure in  !

MODE 3, if capable of being manually realigned and not otherwise inoperable.

Verify each ECCS injection / spray subsystem 31 days

..s manual, power operated, and hutomatic valve I,

) in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.5.1.3 Verify ADS accumulator supply pressure is 31 days {

2 150 psig.

SR 3.5.1.4 Verify each ECCS pump dev ge # In accordance gified flew rate with g wec.,.isd @ with the Inservice J6ci,J hv e3 Testing Program

['[*[c,*d# DIFFERENTIAL Ruel*r *o 4#*"'d p ;ft.,f A h SYSTEM FLOW RATE PRESSURE Wafunll y e.,,h, .-[g',$stel '

m weU

  • PCS 2 6110 gpm 2 128 psid f ' * '"' LPCI 2 7100 gpm 2 24 psid 4

HPCS 2 6110 gpm 2 200 psid (continued)

..)

PERRY - UNIT 1 3.5-4 Amendment No. 69

i ECCS--Shutdown

. 3.5.2 Attachment 3 PY-CEl/NRR-2430L SURVEILLANCE REQUIREMENTS (continued) Pape 6 of 14 SURVEILLANCE FREQUENCY .

t i

SR 3.5.2.2 Verify, for the required High Pressure Core 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />', '

Spray (HPCS) System, the:

a. Suppression pool water level is 2 16 ft 6 in; or l
b. Conde torage tank water volume is 2 ,20,00 al.

34 % 100 SR 3.5.2.3 Verify, for each required ECCS injection /

31 days spray subsystem, the piping is filled with water from the pump discharge valve to the i

injection valve.

4 SR 3.5.2.4 -------------------NOTE--------------------

One low pressure coolant injection (LPCI)  ;

/ ... )

subsystem may be considered OPERABLE during i alignment and operation for decay heat removal, if capable of being manually realigned and,not otherwise inoperable.

Verify each re' quired ECCS injection / spray 31 days subsystem manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

(continued) k n

]

PERRY - UNIT 1 3.5-8 Amendment No. 69

ECCS-Shutdown

. 3.5.2 Attachment 3 PY-CEUNRR-2430L SURVEILLANCER[,QU_IREMENTS (continued) Paae 7 of 14 SURVEILLANCE FREQUENCY

-SR 3.5.2.5

% EsVerify each required ECCSj: ump develops the.with cified flow rate with -. ::: if t:d  ?"-D In accor, the dance M%d QifferehtTilpr::: rey Inservice ,

faaf '*4 ' -~

Testing Program {

%f + , over<en e & r v '

JC4A DIFFE:tENTIAL I 8 '"# * ' #*

+re 4dr=4 1 SYSTEM FLOW RATE PRESSURE

%i*j[j7"j.

ce n ts:nm d 1 y

    • + "'* / / LPCS 2 6110 gpm 2 128 psid dpft",.Ig

[

LPCI- 2 7100 gpm 2 24 psid HPCS 2 6110 gpm 2 200 psid -

SR 3.5.2.6 -------------------NOTE--------------------

Vessel injection / spray may be excluded.

Verify each required ECCS injection / spray 18 months subsystem actuates on an actual or simulated automatic initiation signal.

I  ;

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PERRY - UNIT 1 3.5-9 Amendment No. 69

Containment Vacuum Breakers 3.6.1.11 3.6 CONTAINMENT SYSTEMS A chment 3 PY-CEl/NRR-2430L 3.6.1.11 Containment Vacuum Breakers Page 8 of14 LCO 3.6.1.11 Three containment vacuum breakers shall be OPERABLE and four containment vacuum breakers shall be closed.

APPLICABILITY: H0 DES 1, 2, and 3.

During movement of recently irradiated fuel assemblies in the primary containment.

During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS *

........................__..--NOTE-----

Enter applicable Conditions and Required Actions .of LC0 3.6.1.1, " Primary Containment @ rating" when the containment vacuum relief subsystem leakage results in exceeding overall . containment leakage acceptance criteria.

CONDITION REQUIRED ACTION COMPLETION TIME A. --

NOTE--------- A.1 Close the associated 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> T. Se arate Condition. motor operated

_/ en ry is allowed for' isolation valve, each containment .

vacuum breaker.

AND D

ragaon4/

'A'. 2 Restore containment- 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> One or two containment ^' vacuumBreakerto vacuum breakers not OPERABLE status.

closed.

.08 One required  ;

containment vacuum breaker inoper other reasons.able for -

(continued)

PERRY - lMIT 1 3.6 31 Aurdnent No.102

Containment Humidity Control 3.6.1.12 3.6 CONTAINHENT SYSTEMS 3

^7fg7,gyg-2430t 3.6.,1.12 Containment Humidity Control

"*8* 8 # "

LCO 3.6.1.12 Containment average temperature-to-relative humidity shall be maintained within limits.

APPLICABILITY: MODES 1. 2. and 3.

During movement of recently irradiated fuel assemblies in the primary containment.

During operations with a potential for draining the reactor vessel (0PDRVs). _

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of ICD S A.1 Restore containment 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> not metan ."'"E 1. 2 average temperature-to-relative humidity -

to within limits.

,m .

) (continued) x .,

A.

l PEIM - lMIT 1 3.6 34 Amendnent No.102

Containment Humidity Control iAttachment 3 3.6.1.12 ACTIONS (continued) g 1oo CONDITION REWIRED ACTION COMPLETION TIME B. Required Action and B.1 Be in MODE 3.

associated Completion 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Time of dition A E -

not met in MODE 1, '

2. or 3. B.2 Be .in MODE 4. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> C. Required Action and C.1 Suspend movement of associated Completion Immediately recently irradiated Time of Condition A fuel assemblies in l' not met during the primary movement of recently containment.

irradiated fuel l assemblies in the primary containment, M

or during OPDRVs. C.2 Initiate action to Immediately suspend OPDRVs. l I) SURVFilIANCF RE00TRFMFNT SURVEILLANCE . FREWENCY' SR- 3.6.1.12.1 Verify containment average temxrature- 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to-relative humidity to be wit 11n limits.

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PERRY - LNIT 1 3.6-35 liim e ai No. 102

Diesel Fuel 011. Lube 011. and Starting Air 3.8.3 Attachment 3 m 3.8 ELECTRICAL POWER SYSTEMS

  • pa$$$$ og2m 3.8.3. Diesel Fuel 011. Lube 011. and Starting Air LCO 3.8.3 The stored diesel fuel oil, lube oil. and starting air subsystem shall be within limits for each required diesel generator (DG). .

APPLICABILITY: When associated DG is required to be OPERABLE.

ACTIONS ,

....................................N0Ts'-------------------------------------

Separate Condition entry is allowed for each DG.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more DGs with A.1 Restore fuei oil 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> fuel oil level: level to within-limits.

1. For Div 1 and d Div 2.

< 73.700 1 and a 65.100 al: and

2. For Div 3.- -

< 36.700 al and a 32.000' al.

B. One or more DGs with B.1 Restore lube oil 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> lube oil inventory: inventor

. limits. y to within

1. For Div 1 and Div 2.

< 374 al and a 350' al: and

2. For Div 3. -

< 260 al and a 236 al..

(castma )

PERRY - UNIT 1 3.8-21 Amendment No.94 t a

Reporting RGquirements 5.6 Attachment 3 5.0 ADMINISTRATIVE CONTROLS

' p$[p$243a 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.

5.6.1 Occuoational Radiation Exoosure Reoort A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors), for whom monitoring was required, receiving exposures > 100 mrem /yr and their associated man rem exposure according to wuk and job functions, (e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance),

waste processing, and refueling). This tabulation supplements the requirements of 10 CFR 20.2206. The dose assignments to various duty functions may be estimated based on pocket dosimeter, thermoluminescent dosimeter (TLD), or film badge measurements.

Small exposures totalling < 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources should be assigned to: specific major work functions.

The Occupational Radiation Exposure. Report covering the activities

) of the unit for the previousi:M:;@ year shall be submitted by March 31 of each year. ~y 5.6.2 Annual Radioloaical Environmental Doeratino Report The Annual Radiological Environmental Operating Report covering the operation of the unit'during the previous calendar year shall be submitted by May 1 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated (continued)

PERRY - UNIT 1 5.0-16 Amendment No. 69 '

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1 High Radiation Area 5.7 Attachment 3 5.0 ADMINISTRATIVE CONTROLS PY-CEl/NRR-2430L Page 13 of14 1 5.7 High' Radiation Area 5.7.1 Pursuant to 10 CFR 20, paragraph 20.1601(c), in lieu of the requirements of 10 CFR 20.1601 defined in 10 CFR 20, in which(the intensity of radiation isa), each hig

> 100 mres/hr but < 1000 mres/hr, shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP . Individua ed J:e

  • procedures )(eg@r.ls cualified in radiation protection

<*4d;m ;b-AesTtiichnicians) or personnel continuously escorted by such ndividuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas', provided they are otherwise following plant radiation such high radiation areas. protection procedures for entry into Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a.

lA-radiation monitoring device'that continuously indicates

~ 'the radiation dose rate in the area.

) b.

A' radiation monitoring device that continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel are aware of them, c.

- An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the health physics supervisor in the RWP.

5.7.2 In addition to the requirements of Specification 5.7.1, areas accessible to personnel with radiation levels such that a major l portion of the body could receive in I hour a dose it 1000 mrem shall be provided with locked or continuously. guarded doors to prevent unauthorized entry and the keys shall be maintained under M 'U" .

"-e administrative control of the shift supervisor on duty or the

=d@.upervisor.

fr* * *' dur ng ;^eriods of access by personnel under an approved RW p

(continued)  ;

PERRY - UNIT 1 5.0-19 Amendment No. 69

High Radiation Area 5.7 m

' Attachment 3 5.7 H1gh Radiation Area

, , PY-CEl/NRR-2430L Page 14 of14 5.7.2 (continued)

Individualn oualif ed An radiation protection procedures (e.g7'i =" technicians) or personnel continuously raA@hea **

escofted )y su'c iTndividuals may be exempt from the RWP issuance f requirement during the performance of their assigned duties in high radiation areas with exposure rates s 3000 mrem /hr, provided they are otherwise following plant radiation protection procedures

, for entry into such high radiation areas.

5.7.3 In addition to the requirements of Specification 5.7.1. for individual high radiation areas accessible to personnel with radiation levels such that a major portion of the body could receive in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a dose = 1000 mrem that are located within large areas such as reactor containment, where no enclosure exists for purposes of locking, or that are not continuously guarded, and where no enclosure can be reasonably constructed around the individual area, that individual area shall be barricaded and conspicuously posted, and a flashing light shall be activated as a warning device.

5.7.4 In addition to the r uirements and 5.7.1 and 5.7.2 for Ndividual areas. exemptions accessible of to Specifications personnel such that a major

> 3000 mrem,entry.shall portion ofrequire the body could receive an. approved RWPinwhich 1 hourwilla dose specify dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area. In lieu of the stay time specification of the RWP. continuous surveillance, direct or remote such as use of closed circuit TV cameras, may be made by personn,el qualified in radiation protection procedures to provide positive exposure control over activities within the areas. _

PERRY - UNIT 1 5.0-20 Amendment No. 85

1

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ECCS Instrumentation B 3.3.5.1 4

BASES Attachment 4 I PY-CEl/NRR-2430L Page 1 of14 f

)

l APPLICABLE' 3.c.

SAFETY ANALYSES. Reactor Vessel Water Level-Hiah. Level 8 -(continued)

LCO, and measurement instrumentation. ,

APPLICABILITY in a one-out-of-two taken twice logic.The instruments are arranged!

This ensures that no I single instrument failure can reclude HPCS initiation. The i

Reactor chosen toVessel isolate Water flow fromLevel-H1 t h. Level 8 Allowable Value is j HPCS System prior to water overflowing into the MSLs. j Four channels.of Reactor Vessel Water Level-High. Level 8 Function are only required to be OPERABLE when HPCS is I

required to be OPERABLE. Refer to LC0 3.5.1 and LC0 3.5.2 i for HPCS Applicability Bases.

3.d. Condensate Storaae Tank Level-Low Low level in the CST indicates the unavailability of an adequate supply of makeup water from this normal source. j Normally the suction valve between HPCS and the CST is o)en j and, upon receiving a HPCS initiation signal, water for,iPCS injection would be taken from the CST However, if the water level in the CST falls below a hreselected level, first the su)pression pool suction valve automatically o) ens, and tien the CST suction valve automatically closes.

) T11s ensures that an adequate supply of makeup water is available to the HPCS pump. To prevent losing suction to the pump, the suction valves are interlocked so that the suppression pool suction valve must be open before the CST suction valve automatically closes. The Function is  !

1 malic'tly assumed in the accident and transient analyses (w11ch take credit for HPCS) since the analyses assume that the HPCS suction source is the suppression pool.

Condensate Storage Tank Level-Low signals are initiated from two level transmitters. The logic is arranged such that either transmitter and associated trip unit can cause the suppression pool suction valve to open and the CST suction valve to close. The Condensate M ora do,3ee pa#Ds Function Allowable Value o E' 7% ge Tank Level-Lowieleve N(U (Eld *+,en 4t6fe.I neac rO d h hiah en

. i vi m o ensure aciequate pump suction w11Te wateF is ing taken from the CST.

t .Aes) j Two channels of the Condensate Storage Tank Level-Low Function are only required to be OPERABLE when HPCS is required to be OPERABLE to ensure that no single instrument failure can preclude HPCS swap to the suppression pool source. Thus, the Function is required to be OPERABLE i (continued)

PERRY - UNIT 1 B 3.3-103 Revision No. 1

ECCS Instrumentation B 3.3.5.1 Attachment 4 BASES 4

.-~..

$E2 APPLICABLE'. 3.d.

SAFETY ANALYSES. Condensate Storaae Tank Level-Low (continued)

LCO. and in MODES 1. 2. and 3. In MODES 4 and 5, the Function is APPLICABILITY- required to be OPERABLE only when HPCS is recuired to be OPERABLE to fulfill the requirements of LCO 2.5.2. NPCS is aligned to the CST, and the CST water level is not within the limits of SR 3.5.2.2 and the suppression pool water level is within the limits of SR 3.5.2.2. With CST water

. level within limits. a sufficient supply of water exists for injection to minimize the consequences of a vessel draindown event. Refer to LC0 3.5.1 and LC0 3.5.2 for HPCS Applicability Bases.

3.e. Suooression Pool Water Level-Hioh Excessively high suppression pool water level could result in the loads on the suppression pool exceeding design values should there be a blowdown of the reactor vessel pressure through the S/RVs. Therefore, signals indicating high suppression pool water level are used to transfer the suction source of HPCS from the CST to the suppression pool to eliminate the possibility of HPCS continuing to additional water from a source outside containment. provide To prevent losing suction to the pump, the suction valves are

~

interlocked so that the suppression pool suction valve must be open before the CST suction valve automatically closes.

This Function is implicitly assumed in the accident and transient analyses (which take credit for HPCS) since the analyses assume that the HPCS suction source is the suppression pool.

Suppression Pool Water Level-High signals are initiated from two level transmitters. The logic is arranged such that either transmitter and associated trip unit can cause the suppression pool suction valve to open and the CST suction valve to close. The Allowable Value for the Suppression Pool Water Level-High Function is chosen to ensure that HPCS will be aligned for suction from the suppression pool before the water level reaches the point at which suppression pool design loads would be exceeded.

Two channels of Suppression Pool Water Level-High Function are only required to be OPERABLE in MODES 1. 2. and 3 when

- HPCS is required to be OPERABLE to ensure that no single instrument failure can preclude HPCS swap to suppression pool source. In MODES 4 and 5. the Function is not required to be OPERABLE since the reactor is depressurized and vessel (continued)

PERRY - UNIT 1 8 3.3-104 Revision No. 1 L

RCIC System Instrumentation

. Attichment 4

  • BASES PY-CEl/NRR-2430L Page 3 of 14 APPLICABLE 2.

SAFETY ANALYSES. Reactor Vessel Water Level-Hich. Level 8 (continued)

LCO,and APPLICABILITY into the main steam lines (MSLs). (The injection valve also closes due to the closure of the steam supply valve.)

Reactor Vessel Water Level-High. Level 8 signals for RCIC are initiated from four level transmitters from the wide range water level measurement instrumentation which sense the difference between the pressure due to a constant column of water (reference leg) and the pressure due to the actual water level (variable leg) in the vessel.

-The Reactor Vessel Water Level-High. Level 8 Allowable Value is high enough to preclude isolating the injection valve of the RCIC during normal operation yet low enough to trip the RCIC System prior to water overflowing into the MSLs.

Four channels of Reactor Vessel Water Level-High. Level 8 Function are required to be OPERABLE when RCIC is required to be OPERABLE to ensure that no single instrument failure can preclude RCIC initiation.' Refer to LC0 3.5.3 for RCIC Applicability Bases.

,. 3. Condensate Storace Tank Level-tow

)

Low level in the CST indicates the unavailability of an adequate supply of makeup water from this normal source.

Normally the suction valve between the RCIC pump and the CST  !

is o)en and, upon receiving a RCIC initiation si for TCIC injection would be taken from the CST. gnal, waterif However, the water level in the CST falls below a preselected level.

~first the suppression pool suction valve automatically open's and then the CST suction valve automatically closes. This ensures that an adequate supply of makeup water is available to the RCIC pump. To prevent losing suction to the pump, the suction valves are interlocked so that the suppression pool suction valve must be open before the CST suction valve automatically closes.

Condensate Storage Tank Level-Low signals are initiated from two level transmitters. The logic is arranged such that either transmitter and associated trip unit can cause the suppression pool suction valve to open and the CST suction 9ej-3oo pl/ev5 valve to close. The Condensa Storage Tank Level-Low We*g g(,p. Fun n Allowable Value of ..,00 gr : = 'c:avation 524 ft-Q '" , ) , Sche- is high enough to nsure adeguate pump suction head white water is being, aken from the CST.

(continued)

PERRY - UNIT 1 8 3.3-127 Revision No. O

l' t RCIC System Instrumentation B 3.3.5.2 BASES PY-CEl/NRR-2430L Page 4 of14 APPLIGABLE - 3. Condensate Storaae Tank Level-Low (continued)

SAFETY ANALYSES, LCO. and Two channels of Condensate Storage Tank Level-Low Function APPLICABILITY' are required to be OPERABLE when RCIC is required to be OPERABLE to ensure that no single instrument failure can

)reclude RCIC swap to the suppression pool source. Refer to

.C0 3.5.3 for RCIC Applicability Bases.

4. Sunoression Pool Water Level-Hiah i

Excessively high suppression pool water level could result in the loads on the suppression pool exceeding design values-should there be a blowdown of the reactor vessel pressure through the safety / relief valves. Therefore, signals indicating high suppression pool water level are used to transfer the suction source of RCIC from the CST to the suppression pool to eliminate the possibility of RCIC continuing to provide additional water from a source outside rimary containment.

1)he NRC Policy Statement.This t To preventFunction losingsatisfies Criterion suction to the 3 of

. pump, the suction valves are iriterlocked so that the suppression pool suction valve must be open before the CST suction valve automatically closes, i

'" Suppression Pool Water Level-High signals are initiated from two level transmitters. The logic is arranged such that either transmitter and associated trip unit can cause the suppression pool suction valve to open and the CST suction valve to close. The Allowable Value for the Suppression Pool Water Level-High Function is chosen to ensure that RCIC l will be aligned for suction from the suppression pool before the water level reaches the point at which suppression pool l design loads would be exceeded.

Two channels of Suparession Pool Water Level-High Function are required to be OPERABLE when RCIC is required to be OPERABLE to ecsure that no single instrument failure can preclude RCIC swap to the supl>ression pool source. If the .

automatic transfer of the suction source for RCIC from the CST to the suppression pool, due to a high suppression pool water level signal, is manually overridden by the operator, then the Suppression Pool Water Level-High Functions are considered ino>erable. Refer to LC0 3.5.3 for RCIC

, Applicability 3ases.

(continued)

PERRY-- UNIT 1 B 3.3-128 Revision No.1

ECCS-Shutdown B 3.5.2 BASES Attachment 4 PY-CEl/NRR-2430L Page 5 of 14 SURVEILLANCE REQUIREMENTS SR 3.5.2.1 ans SR 3.5.2.2 (continued)

=16ft6inchesortheHPCSSystemisaligneddtake "'###

suction from the CST and the CST contains =C20.00Pgallons of water, assuring 150,000 gallon HPCS,equivalenttoavolumeof of water available for System can supply makeup water nsures that the HPCS to t RPV.

The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Frequency of these SRs was developed considerin operating experience related to suppression pool and CST water level variations.during the applicable MODES.

Furthermore, the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Frequency is considered adecuate in view of other indications in the control room, inclucing alarms, to alert the operator to an abnormal suppression pool or CST water level condition.

SR 3.5.2.3. SR 3.5.2.5 and SR 3,5.2.6 The Bases provided for SR 3.5.1.1. SR 3.5.1.4. and SR 3.5.1.5 are applicable to SR 3.5.2.3, SR 3.5.2.5, and s..

SR 3.5.2.6. respectively, SR 3.5.2.4 Verifying th'e correct alignment for manual, power operated, and automatic valves in the ECCS flow paths provides operation. that assurance the proper flow paths will . exist for ECCS This SR does not apply to valves that are locked, sealed or otherwise secured in position since these valves were ver,ified to be in the correct position prior to locking, sealing, or securing. A valve that receives an initiation signal is allowed to be in a nonaccident position provided the valve will automatically reposition in the proper system response time. This SR does not require any testing or valve manipulation: rather, it involves verification that those valves potentially ca)able of being mis ositioned are in the correct position. T11s SR does not app y to valves that cannot be inadvertently misaligned, suc as check valves. The 31 day Frequency of this SR was derived from the Inservice Testing Program requirements for (continuedL PERRY - UNIT 1 B 3.5-19 Revision No.1

ECCS-Operating B 3.5.1

' C BASES Attachment 4

, , , PY-CEt/NRR-2430L Page 6 of14 SURVEILLANCE REQUIREMENTS SR 3.5.1.2 (continued) capable of being manually realigned (remote or local) to the LPCI mode and not otherwise inoperable. This allows operation in the RHR shutdown cooling mod.e during MODE 3 if necessary.

SR 3.5.1.3 Verification every 31 days that ADS accumulator supply pressure is = 150 psigiassures adequate air pressure for reliable ADS operation. The accumulator on each ADS valve provides pneumatic pressure for valve actuation. The designed pneumatic supaly pressure requirements for the accumulator are such t1at, following a failure of the pneumatic supply to the accumulator, at least two valve

. actuations can occur with the drywell at 70% of design pressure (Ref.13).

The ECCS safety analysis assumes only one actuation to achieve the depressurization required for operation of the low pressure ECCS. This minimum required

^

pressure of 150 psig is provided by the Safety Related Instrument Air System. The 31 day Frequency takes into s

consideration administrative control over operation of the Safety pressure.Related Instrument Air System and alarms for low air 4

SR 3.5.1.4 i The performance requirements of the ECCS pumps are determined through ap)lication of the 10 CFR 50 Appendix K, criteria (Ref. 8). T11s periodic Surveillance is performed (in accordance with the ASME Code,Section XI, requirements l for the ECCS pumps) to verify that the ECCS pumps will develop the flow rates required by the respective analyses. t The ECCS pump flow rates ensure that adequate core cooling is provided to satisfy the acceptance criteria of 10 CFR 50.46 (Ref. 10).

/ees..

  • neo e pifl~ [e[e :r: ;;rified =ith : pg dbf:r;,,ti:1 pres:Cr:

-e th:t i: :ufficier; v t^d duri~; LaCf.. te eJerce.T.e i. .c RP" pieasdre-paragrafi is ed=9ete te e"erc^-^ th:M 0000 puny uiiic, c ,;..el are3 acre-Olcvat.v. heed pico.uie .; eta;;..

the

, p" p rect 4= end the vessel di:ch rg;, the pipir,g-(continued)

PERRY - UNIT l' B 3.5-10 Revision No. O

SA 5,I,/,4 Pedew.4) Attrchment 4 PY-CEl/NRR-2430L Page 7 of 14 The ECCS pump differential pressure for each listed system in the Surveillance

, Requirements (SRs) 3.5.1.4 and 3.5.2.5, is the difference between the containment

{

wetwell pressure and the RPV pressure assumed in the LOCA analyses at the time of injection / spray. In addition to this listed differential pressure, the ECCS pumps also need to overcome elevation head loss and piping system friction loss at the required flow rate.

This safety analysis value is determined by engineering calculation. In addition, ptunp operability may be limited by the ASME " required action" range value for these pumps.

F

. - , , . j i

ECCS-Operating B 3.5.1 t -

/ Attachment 4 BASES

, , , PY-CEl/NRR-2430L Page 8 of 14 SURVEILLANCE REQUIREMENTS SR 3.5.1.4 (continued)

J'~~

fricti= let:c . 2M PP" presterc prcsont durin LOCAs.

W. :: =hc: =v be eelduiisneo ouring ure uve,sA wel t :ti=.rThe Frequency for this Surveillance is n accordance with the Inservice Testing Program requirements.  !

SR 3.5.1.5 i i

The ECCS subsystems are required to actuate automatically to i perform their design functions. This Surveillance test verifies that, with a required system initiation signal ,

(actual or simulated), the automatic initiation logic of HPCS, LPCS, and LPCI will cause the systems or subsystems to i i

o>erate as designed, including actuation of the system tiroughout its emergency operating sequence, automatic pump startup, and actuation of all automatic valves to their required positions. This Surveillance also ensures that the HPCS System will automatically restart.on an RPV low water level (Level 2) signal received subsequent to an RPV high water level (Level 8) trip and that the suction is l t automatically transferred from the CST to the suppression pool on a condensate storage tank low water level signal and on a sunression pool high water level signal. The LOGIC SYSTEM

JNCTIONAL TEST performed in LC0 3.3.5.1, " Emergency Core Cooling System (ECCS) Instrumentation," overlaps this Surveillance to provide complete testing of the assumed i safety function.

HPCS testing may be performed in any MODE. The Frequency of 18 months is based upon operating experience that has shown these components usually pass the Surveillance when performed at the 18 month Frequency.

With the exce] tion of the HPCS LOGIC SYdTEM FUNCTIONAL TEST, the 18 month requency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an un)lanned transient if the Surveillance were performed with tie reactor at power.

Operating experience has shown that these components usually pass the SR when performed at the 18 month Frequency, which is based on the refueling cycle. Therefore, the Frequency

-was concluded to be acceptable from a reliability standpoint.

(continued)

PERRY - UNIT 1 B 3.5-11 Revision No. 1

o

' Primary Containment and Drywell Isolation Instrumentation B 3.3.6.1 Attachment 4 i

BASES haggg24m APPLICABLE SAFETY ANALYSES, 3.a. Main Steam Line Pine Tunnel Temoerature Timer (continued)

LCO. and APPLICABILITY The Allowable Values are based on maximizing the .

availability of the RCIC System: that is, providing' sufficient time to isolate all other potential leakage sources in the main steam tunnel before RCIC is isolated.

This Function isolates the Group 9 valves.

3.1. RCIMteam Line Flow-Hiah RCIC N high steam line 'l is provided to detect a break f the si.neey steam line er i i: r ccr.=rd =" w-and initiates closure of the isolatisivalves forsg g If the steam were allowed to continue flowing ou o the break, the reactor would depressurize and the core could uncover. Therefore, the isolation is initiated at high flow to prevent or minimize core damage. Specific credit for this Function is not assumed in any USAR accident or transient analysis since the bounding analysis is

)erformed 3reaks. However.forthese large breaks instruments such prevent the as RCI recirculation W a

,] '

steam line break from becoming bounding.

The RCICdsteam line flow signals are initiated from two transmitters that are connected to the steam line. .Two 4 channels wjth one channel in each trip. system are required i to be OPERABLE to ensure that no single instrument failure can preclude the isolation function. The Allowable Value is selected to ensure that the trip occurs to prey _ent fuel  ;

damage and maintains the MSLB as th ent.

um This Function actuates the Group 9 va 1

3.1. Drvwell Pressure-Hiah  !

High drywell pressure can indicate a break in the RCPB. The '

RCIC isolation of the turbine exhaust is provided to prevent communication with the drywell when high drywell pressure exists. A )otential~ leakage path exists via the turbine

exhaust. T1e isolation is delayed until the system becomes unavailable for injection (i.e., low steam line pressure).

The isolation of the RCIC turbine exhaust by Dr.ywell Pressure-High is indirectly assumed in the USAR accident '

analysis because the turbine exhaust leakage path is not assumed to contribute to offsite doses.

i.

(continued)

_ .) -

PERRY - UNIT 1 B 3.3-154 Revision No. 1

r Containment Humidity Control B 3.6.1.12

~

B, 3,6 . CONTAINMENT SYSTEMS Attachment 4 yE 2430L B 3.6.1.12 Containment Humidity Control BASES '

BACKGROUND Primary containment tencerature and humidity are initial condition inputs into t1e analysis that evaluates the initiation of RHR containment spray during normal plant operation.

A curve was determined of initial 3rimary containment average temperature and humidity witch would maintain peak vacuum inside containment s 0.72 psi (design is s 0.80 psi) during the spray initiation event. This curve then determines the containment average temperature-to-humidity combinations that are acceptable whenever the conditions exist for the inadvertent containment spray initiation event (whenever the primar tight barrier has been established). y containment leak I APPLICABLE  ;

SAFETY ANALYSES Reference 1 contains the results of analyses that predict the primary containment pressure response for the s inadvertent initiation of the RHR Containment Spray System. j

~

1 The initial containment average temperature and relative humidity have an effect on the results of this analyses. As i long as the average temperature and. relative humidity is maintained within the limits of Figure B 3.6.1.12-1, the design can adequately perform in the inadvertent containment spray event.

There is no need to monitor the containment average temperature-to-relative humidity when the primary containment is not OPERABLE (i.e. has large enough openings i such that a vacuum would not be created during an RHR containment.sprayevpnt).

The cont'ainment relative humidity satisfies Criterion 3 of the NRC Policy Statement.

LC0 In the event RHR containment spray initiates during normal plant conditions, and while~ the primary containment is required to be OPERABLE the initial average temperature and relative' humidity must be within defined limits in order to assure proper response of the )rimary containment. When the primary containment is not OPEMBLE, and contains sufficient openings such that a vacuum would not be created during a containment spray initiation, the average temperature and j _

coritinued) i 1

PERRY - UNIT 1 B 3.6-65 Revision No. 1 4

c

.. BASES

.ContainmentHumidigyCgn{rg Attachment 4 3. . .

PY-CEl/NRR-2430L Page 11 of 14 LC0 (continued) relative the humidity prescribed are not required to be maintained within limits.

APPLICABILITY In MODES 1. 2. and 3. the RHR Containment Spray System is required to be OPERABLE to mitigate the effects of a DBA.

Excessive negative pressure inside the containment could occur due to inadvertent actuation of this system. The containment average temperature relationship with relative humidity, therefore, is required to be within limits in MODES 1, 2. and 3. to mitigate the effects of inadvertent actuation of the RHR Containment Spray System.

l In MODES 4 and 5. the probability and consequences of these events are reduced by the pressure and temperature limitations in these MODES. Therefore, maintaining limits on containment relative humidity and temperature is not required in MODE 4 or 5.

When handling recently irradiated fuel in the primary

" containment, and during operations with a potential for rimary containment j

)

- drain is r uiredng the to be reactor vessel OPERABLE. Therefore,(0PDRVs) t the ge propj relationship between containment average ~ temperature and relative humidity must exist during these evolutions. Due to radioa.ctive decay, handling of fuel only' requires control

j over. Containment. humidity when the fuel being ha6dled is recently:1rradiated, i.e., fuel that has occupied part of a critical rbactor core within the previous seven days.

ACTIONS 6.l With the primary containment average temperature and relative humidity'not within the established limits, actions must.be taken to restore the primary containment mlat' ve

=humidity and temperature to within limits. CC: " M' g .

=im = WA L ?. 'D Required Action A.1 stipu' ates

';1at res';orat1on must occur within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. The eight hour i Completion Time is based on the time required to restore the  !

relative humidity and temperature limits, and the low '

probabil.1_ty of an event occurring during this time period.

(ccM.inued) i N./

PERRY - UNIT 1 B 3.6-66 Revision No. 2

E r f t, .

ContainmentHumidigygng Attachment 4

. BASES- -

PY-CEl/NRR-2430L Paoe 12 of 14 ACTIONS B.1 and B.2 (continued)

If the cannot 3rimary containment relative humidity and temperature

>e restored to within limits within the required Completion place the Time of Condition A, actions must be taken to not apply. plant in a MODE or condition in which the LCO does l

Required Action B.1 and requires lant be brou that the hed Action B least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Requi .

requires that the plant be brought to MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.

C.1 and C.2 If the primary containment relative humidity and temperature

-(w.-) C o, / 6 #- ?q c r.;t h" "- t:18Dring movement of recently irradiated reshd io fuel in Ine primary containment, or during OPDRVs, action is required to place the plant.in a MODE or condition in which ww!'Wl'*IT m+ue. pad the LC0 ,does.not apply. " -

coqis;,,, A.

Required Actions C.1 and C.2 require that actions be taken

e,,, asef., A to immediately suspend activities that represent a potential for releasing significant amounts of radioactive material, thus placing.the unit in a condition that minimizes risk.

If applicable, movement of recently irradiated fuel in the primary containment must be suspended immediately.

Suspension of these' activities shall not preclude completion '

of movement of.a component to a safe position. Also, if applicable, actions must be taken to suspend OPDRVs to minimize the probability of a vessel draindown and subsequent potential for fission product release. Actions must continue until OPDRVs are suspended.

(continued)

.d PERRY - UNIT 1 B 3.6-67 Revision No. 2

f n..

.r..

Containment Humidity Control B 3.6.1.12 i A chment 4 BASES (, continued) PY-CEI/NRR-2430L l Page 13 of14 SURVEILLANCE SR 3.6.1.12.1 REQUIREMENTS Verifying that the primary containment average temperature and relative humidity a e within limits ensures that r

operation remains withiri limits assumed in the primary containment (Ref. 1). analyses for initiation of RHR containment spray The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency of this SR is considered acceptable based on the observed slow rates of temperature and relative humidity changes within the primary containment due to the large volume of the primary containment.

REFERENCES 1. USAR. Section 6.2.1.1.4.2.

2.

i

/

PERRY - UNIT 1 B 3.6-68 Revision No. I

7

. . ~ , .

Containment Humidity Control B 3.6.1.12 Attachment 4 PY-CEl/NRR-2430L Page 14 of14 100 t . .

1 90 ,

I =

70 ..

60

- ACCEPTABLE OPERATION

= 50 , ,,

l 2 '

E <-

  • 40  :'

E ,

e . .

30 '

^^~

=

e ,,-

a to - --

r' UNACCEPTABLE
:::

10 . . -

OPERATION'  : -

= = - -

0 "

' ~~ ~

60 70 80 90 100 110 120 I

Temperaturo (*F)

CONTAINMENT AVERAGE TEMPERATURE vs RELATIVE HUMIDITY Figure B 3.6.1.12-1 '

l l

l l

.)

PERRY - UNIT 1 B 3.6--69 Revision No.1

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