ML20077B186

Proposed Tech Specs 3.5.F,4.5.F.1 & 3.9.B.1 & 2 Re EDG Allowed out-of-svc Time

ML20077B186
Person / Time
Site:	Pilgrim
Issue date:	11/22/1994
From:	BOSTON EDISON CO.
To:
Shared Package
ML20077B183	List: BECO-94-126, Application for Amend to License DPR-35,increasing Current EDG Allowed out-of-svc Time in Specification 3.5.F from 72 H to 7 Days ML20077B186
References
NUDOCS 9411280301
Download: ML20077B186 (9)

Text

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. LIMITING CONDITION FOR OPERATION SURVEILLAWCE REQUIREMENT 3S CORE AND CONTAINMENT COOLING 4.5 CORE AND CONTAINMENT COOLING SYSTEMS (Cont) SYSTEMS (Cont)

F. Minimum Low Pressure Coolinn and F. Minimum Low Pressure Cooline. and Diesel Generator Availability Diesel Generator Availability

1. During any period when one 1. (Intentionally left blank) diesel generator is inoperable, continued reactor operation is permissible only during the l succeeding 7 days unless such diesel generator is sooner made operable, provided that all of the low pressure core and contairunent cooling systems and the remaining diesel generator shall be operable If this requirement cannot be met, an orderly shutdown shall be initiated and the reactor shall be placed in the Cold Shutdown Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2. Any combination of 1.noperable components in the core and containment cooling systems shall not defeat the capability of the remaining operable components to fulfill the cooling functions.

3. When irradiated fuel is in the reactor vessel and the reactor is in the Cold Shutdown condition, both core spray systems, the LPCI and containment cooling systems may be inoperable, provided no work is being done which has the potential for draining the reactor vessel. I

4. During a refueling outage, f or a period of 30 days, refueling operation may continue provided that one core spray system or .

the LPCI system is operable or Specification 3.S.F.5 is met.

Amendment No. 15 r -l M 3/4.5-7 9411290301 9411"  !

PDR ADOCK 05000293 P PDR l 1

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. BASES: l 3.5 CORE AND CONTAINMENT COOLING SYSTEMS (Cont) occur. A potential draining of the reactor vessel (via control rod blade leakage) would allow this water to enter into the torus and after approximately 140,000 gallons have accumulated (needed to meet minimum NPSH requirements for the LPCI and/or core spray pumps), the torus would be able to l serve as a common suction header. This would allow a closed loop opeiration of '

the LPCI system and the core spray system (once re-aligned) to the torus. In addition, the other core spray system is lined up to the condensate storage tanks which can supplement the refuel cavity and dryer / separator pool water to provide core flooding, if required.

Specification 3.9 must also be consulted to determine other requirements for the diesel generators.

The Emergency Diesel Generator Out-of-Service time is set at 7 days to allow for maintenance, repair and testing of the out-of-service EDG in an orderly fashion, without challenging the other systems for shutdown transients.

The verification of the corree c breaker aligtunent and indicated power availability for each offsite circuit provides assurance that offsite power is available when one EDG is out-of-service.

G. Deleted H, Maintenance of Filled Discharne Pipe If the discharge piping of the core spray, LPCI system, HPCI, and RCIC are not filled, a water hammer can develop in this piping when the pump and/or pumps l are started. An analysis has been done which shows that if a water hammer were to occur at the time at which the system were required, the system would still perform its design function. However, to minimize damage to the discharge piping and to ensure added margin in the operation of these systems, this Technical Specification requires the discharge lines to be filled whenever the system.is in an operable condition.

4.5 COPE AND CONTAINMENT COOLING SYSTEMS SURVEILLANCE FREQUENCIES I

The testing interval for the core and containment cooling systems is based on' industry practice, gaantitative reliability analysis, judgment and practicality. The core cooling systems have not been designed to be fully testable during operation. For example, in the case of the HPCI, automatic j initiation during power operation would result in pumping cold water into the i reactor vessel which is not desirable. Complete ADS testing during power operation causes an undesirable loss-of-coolant inventory. To increase the ,

availability of the core and containment cooling systems, the components which' '

make up the system; i.e., instrumentation, pumps, valves, etc., are tested j frequently. The pumps and motor operated valves are tested in accordance with j ASME B&pV Code,Section XI (IWP and IWV, except where specific relief is  ;

granted) to assure their operability. I 1

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Amendment No. 392 -135 1-140 B3/4.5-6 l

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BASES:

4,. 5 CORE AND CONT,i1NMENT C001.ING SYSTEMS SURVEILLANCE FREQUENCIES (Cont)

The_ frequency and methods of testing are described in the PNPS IST program.

The PNPS IST Program is used to assess - the operational ~ readiness of pumps and valves that are safety-related or important t o s a f e ty . When components are

, tested and found inoperable the impact on system operability is determined, and corrective action or Limiting Conditions of Operation are initiated. A simulated automatic actuation test once each cycle combined with code inservice testing of-the pumps and valves is deemed to be adequate testing of these systems.

The surveillance requirements provide adequate assurance that the core and containment cooling systems will be operable when required.

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5 Amendment No. 39;-135 7 -149 B3/4.5-7

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS

3. 9 AUXILIARY ELECTRICAL SYSTEM (Cont) 4.9 AUXTLI ARY ELECTRICAL SYSTEM (Cont)

B. Operation with Inoperable A. Auxiliary Electrical Equipment Equipment Surveillance (Cont)

Whenever the reactor is in Run 3. Emergency 4160V Buses A5-A6 Mode or Startup Mode with the Degraded Voltage Annunciation reactor not in a Cold Condition, System.

the availability of electric power

a. Once each operating cycle, shall be as specified in 3.9.B.1, calibrate the alarm sensor.

3.9.B.2, 3.9.B.3, 3.9.B.4, and 3.9.B,5.

b. Once each 31 days perform a channel functional test on

1. From and after the date that the alarm system.

Incoming power is not available from the startup or shutdown c. In the event the alarm transformer, continued reactor system is determined operation is permissible under inoperable under 3.b above, this condition for seven days. commence logging safety During this period, both diesel related bus voltage every 30 generators and associated minutes until such time as l emergency buses must be the alarm is restored to operable. operable status.

2. From and after the date that 4. RPS Electrical Protection ,

incoming power is not available Assemblies l from both startup and shutdown transformers, continued a. Each pair of redundant RPS  !

operation is permtssible, EPAs shall be determined to I be operable at least once I provided both diesel generators and associated emergency buses per 6 months by performance are operable, all core and of an instrument functional containment cooling systems are test l operable, reactor power level is reduced to 25% of design and b. Once per 18 months each pair the NRC is notified within one of redundant RPS EPAs shall (1) hour as required by be determined to be operable 10CFR50.72. by performance of an instrument calibration and

3. From and after the date that by verifying tripping of the one of the diesel generators or circuit breakers upon the associated emergency bus is simulated conditions for

, made or found to be Inoperable automatic actuation of the for any reason, continued protective relays within the reactor operation is following limits:

permissible in accordance with Specification 3.5.F if Overvoltage s 132 volts Specification 3.9.A.1 and Undervoltage 'e 108 volts 3.9.A.2.a are satisfied. Underfrequency 'e 57H z

4. From and after the date that one of the diesel generators or associated emergency buses and either the shutdown or startup transformer power source are Amendment No. 8 % -127--1457 -151 3/4.9-4

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. . . 1 ATTACHMENT C to BECo Letter 94-126 Marked-up Paaes from Current Technical Specifications l

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LIMYTING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT

,3 . 5 ' CORE AND CONTAINMENT COOLING 4.5 CORE AND CONTAINMENT COOLING SYSTEMS (Cont) SYSTEMS (Cont)

F. Minimum Low Pressure Coolinn and F. Minimum Low Pressure Cooline and Diesel Generator Availability Diesel Generator Availability

1. During any period when one 1.[7henit is determined that one3 diesel generator is inoperable, (diesel generator is inoperable,;

continued reactor operation is the operable diesel generator permissible only during the shall be demonstrated to be succeeding <72JsT> r) unless such operable immediately and daily diesel generator is's oner made i thereafter until the inoperabl operable, provided that < 1Lof \"diesel

" ~ ~is re gaired._ - _ k the low pressure core and

\s 7dap containment cooling systems and the remaining diesel generator shall be operable. If this requirement cannot be met, an s Qall7 { C h4 orderly shutdown shall b'e b initiated and the reactor shall be placed in the Cold Shutdown Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2. Any combination of inoperable components in the core and containment cooling systems shall not defeat the capability of the remaining operable components to fulfill the cooling functions.

3. When irradiated fuel is in the reactor vessel and the reactor it in the Cold Shutdown candition, both core spray sy items , the LPCI and containment cooling systems may be inoperable, provided no work  ;

is being done which has the ,

potential for draining the  !

reactor vessel. j

4. During a refueling outage, for a I I

period of 30 days, refueling operation may continue provided that one core spray system or the LPCI system is operable or Specification 3.5.F.5 is met.

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(Revision 177) - %

AmendmeriENo . H--l M 3/4.5-7  !

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. - PASES:

3,5 CORE AND CONTAINMENT COOLING SYSTEMS (Cont) occur. A potential draining of the reactor vessel (via control rod blade leakage) would allow this water to enter into the torus and after approximately 140,000 gallons have accumulated (needed to meet minimum NPSH requirements for the LPCI and/or core spray pumps), the torus would be able to serve as a common suction header. This would allow a closed loop operation of the LPCI system and the core spray system (once re-aligned) to the torus. In addition, the other core spray system is lined up to the condensate storage tanks which can supplement the refuel cavity and dryer / separator pool water to provide core flooding, if required.

Specification 3.9 must also be consulted to determine other requirements for the diesel yf merat. ors .

I A3d'p .

,s

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b G. Deleted H. Maintenance of Filled Discharne Pipe If the discharge piping of the core spray, LPCI system, HPCI, and RCIC are not filled, a water hammer can develop in this piping when the pump and/or pumps are started. An analysis has been done which shows that if a water hammer were to occur at the time at which the system were required, the system would still perform its design function, However, to minimize damage to the discharge piping and to ensure added margin in the operation of these systems, this Technical Specification requires the discharge lines to be filled whenever the system is in an operable condition.

4.5 CORE AND CONTAINMENT COOLING SYSTEMS SURVEILLANCE FREQUENCIES The testing interval for the core and containment cooling systems is based on industry practice, quantitative reliability analysis, judgment and

' practicality. The core cooling systems have not been designed to be fully testable during operation, For example, in the case of the HPCI, automatic initiation during power operation would result in pumping cold water into the reactor vessel which is not desirable. Complete ADS testing during power operation causes an undesirable loss-of-coolant inventory. To increase the availability of the core and containment cooling systems, the components which make up the system; i.e., instrumentation, pumps, valves, etc., are tested frequently. The pumps and motor operated valves are tested in accordance with ASME B&PV Code.Section XI (IWP and IWV, except where specific relief is granted) to assure their operability. The frequency and methods of testing are described in t he PNPS IST program. The PNPS IST Program is used to assess the operational readiness of pumps and valves that are safety-related or When components are tested and found inoperable the important to safety.

impact on system operability is determined, and corrective action or Limitin5 Conditions of Operation are initiated. A simulated automatic actuation test once each cycle combined with code inservice testing of the pumps and valves is deemed to be adequate testing of these systems.

ihe surveillance requirements provide adequate assurance that the core and containment cooling systems will be operable when required.

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Revision 1G

([X5Fridih6HI~~No 392-135. -14u B3/4.5 6

Insert A l

I The Emergency Diese1 Generator Out-of Service time is set at 7 l days to allow for maintenance, repair and testing of the out-of- 1 service EDG in an orderly fashion, without challenging the other j systems for shutdown transients. l The verification of the correct breaker alignment and indicated j power availability for each offsite circuit provides assurance  ;

that offsite power is available when one EDG is out-of-service.  !

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> , LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9 ' AUXILIARY ELECTRICAL SYSTEM (Cont) 4.9 AUXIIIARY ELECTRICAL SYSTEM (Cont)

B. Operation with Inoperable A. Auxiliary Electrical Eauipment Eauipment Surveillance (Cont)

Whenever the reactor is in Run 3. Emergency 4160V Buses AS-A6 Mode or Startup Mode with the Degraded Voltage Annunciation 3 7 8'***

reactor not in a Cold Condition, the availability of electric power shall be as specified in 3.9.B.1'

a. Once each operating cycle, calibrate the alarm sensor.

3.9.B.2, 3.9.B.3, 3.9.B.4, and 3.9.B.S. b. Once each 31 days perform a channel functional test on

1. From and after the date that the alarm system.

incoming power is not available from the startup or shutdown c. In the event the alarm transformer, continued reactor system is determined operation is permissible under inoperable under 3.b above, this condition for seven days. commence logging safety During this period, both diesel related bus voltage every 30 generators and associated minutes until such time as emergency buses must be the alarm is restored to diem 9nsnated to7Ad operable. operable status.

N 2, From and after the date that 4. RPS Electrical Protection incoming power is not available Assemblies from both startup and shutdown transformers, continued a. Each pair of redundant RPS operation is permissible, EPAs shall be determined to provided both diesel generators be operable at least once and associated emer (ency busec per 6 months by performance are (demonstrated _tn_he9 % of an instrument functional operable, all core and test, containment cooling systems are operable, reactor power level b. Once per 18 months each pair is reduced to 25% of design and of redundant RPS EPAs shall the NRC la notified within one be determined to be operable (1) hour as required by by performance of an 10CFR50.72. instrument calibration and by verifying tripping of the

3. From and after the date that circuit breakers upon the one of the diesel generators or simulated conditions for associated emergency bus is automatic actuation of the made or found to be inoperable protective relays within the for any reason, continued following limits:

reactor operation is permissible in accordance with ove rvoltage < 132 volts Specification 3.5.F if Undervoltage 2 108 volts Specification 3.9.A.1 and Underfrequency 2 57H z 3.9.A.2.a are satisfied.

4. From and after the date that one of the diesel generators or associated emergency buses and either the shutdown or startup

_ _ transformer power source are ggis ion 1 TT4-~,,

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Ameddiiiesit No. 88:-127:-145:.151 3/4.9-4

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