ML20217F934

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Proposed Tech Specs Re EDG Allowed Outage Time
ML20217F934
Person / Time
Site: Pilgrim
Issue date: 03/26/1998
From:
BOSTON EDISON CO.
To:
Shared Package
ML20217F933 List:
References
NUDOCS 9804010304
Download: ML20217F934 (6)


Text

. . '. ~

6HAQHMENT C

. . Revised TS Pages and Bases Applicable for EDG AOT Change TS Pages 3/4/5-7,3/4.9-4,3/4.9-5, and Bases Pages 83/4.5-22 and 23 9804010304 900326 PDR ADOCK 05000293 P PDR E

~ LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.5 CORE AND CONTAINMENT 4.5 CORE AND CONTAINMENT COOLING SYSTEMS (Cont) COOLING SYSTEMS (Cont)

Fc Minimum Low Pressure Coolina and F. Minimum Low Pressure Coolina and Diesel Generator Availability Diesel Generator Availability

1. During any period when one 1. When it is determined that one emergency diesel generator EDG is inoperable, within 24 l (EDG) is inoperable, continued hours, determine that the reactor operation is permissible operable EDG is not inoperable l only during the succeeding 72 due to a common cause failure, hours unless such EDG is I sooner made operable, provided OR that all of the low pressure core and containment cooling perform surveillance 4.9.A.1.a systems shall be operable, and for the operable EDG' l the remaining EDG shall be AND operable in accordance with  !

4.5.F.1. If this requirement within I ht ur 7.nd once every 8 cannot be met, an orderly hours thert.after, verify correct shutdown shall be initiated and breaker alignment and indicated the reactor shall be placed in the Cold Shutdown Condition within power circuit. awilability fo[r each offsite ,

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. - l

2. Confirm the Station Black Out The 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO can be Diesel Generator (SBO-DG) has extended to 14 days provided, in been demonstrated operable I addition to the above within the preceding 7 days i requirements, the Station Black i Out Diesel Generator is verified OR operable in accordance with 4.5.F.2. within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of declaring an
2. Any combination of inoperable EDG inoperable, perform a components in the core and surveillance to demonstrate that containment cooling systems the SBO-DG is operable, shall not, defeat the capability of AND the remaining operable '

components to fulfill the cooling within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of demonstrating the functions.

SBO-DG operability as specified  ;

above and once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />

3. When irradiated fuelis in the reactor vessel and the reactor is thereafter, verify normal breaker >

in the Cold Shutdown condition, configuration.

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.

4. During a refueling outage, for a 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.

Amendment No. 15,135,170 3/4.5-7

1 Minimum Low Pressure Cooling snd Diesel Geners.t: r AVIllability 3/4.5.F 1 B 3/4.5 CORE AND CONTAINMENT COOLING SYSTEMS I 3/4.5.F. Minimum Low Pressure Cooling and Diesel Generator Availability

, BASES BACKGROUND The purpose of Specification 3/4.5.F is to assure that adequate core cooling equipment is available at all times. If, for example, one core spray were out of service and the diesel which powered the opposite core spray were out of service, only 2 LCPI pumps would be available.

It is during refueling outages that major maintenance is performed and during such time that all low pressure core cooling systems may be out of service. This specification provides that should this occur, no work will be performed on the primary system which could lead to draining the vessel. This work would include work on certain control rod drive components and recirculation system.

Specification 3.4.F.5 allows removal of one CRD mechanism while the torus is in a drained condition without compromising core cooling capability. The available core cooling capability for a potential draining of the reactor vessel while this work is performed is based on an estimated drain rate of 300 gpm if the control rod blade sealis unseated. Flooding the refuel cavity and dryer / separator pool to elevation 114'-0" corresponds to approximately 305,000 gallons of water and will provide core cooling capability in the event leakage from the control rod drive does 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 243,000 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.

ACTION The maximum allowed out-of-service (OOS) time for one EDG is 14 days, provided that one EDG and the SBO-DG are operable, in addition to all of the low pressure core and containment cooling systems as specified in 3.5.F.1. If the SBO-DG is determined to be inoperable, the maximum allowed OOS time for one EDG is 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

A 24-hour LCO will control the plant for cold shutdown if the SBO-DG becomes inoperable anytime after 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during a 14-day EDG LCO.

SURVEILLANCE The SBO-DG shall be determined to be operable as defined below for extending the 3 days OOS time to 14 days for an EDG. The SBO-DG is operable if a surveillance was completed within the last seven days before extending to a 14-day OOS; otherwise, a surveillance must be completed to demonstrate that the SBO-DG is operable. The 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> period allows the operators to complete the required SBO-DG surveillance using the 23Kv offsite power source and to notify Commonwealth Electric of the needed use of the 23Kv line in the testing configuration. The SBO-DG is operable if it is capable of Amendment No. B3/4.5-22 l

, Minimum Low Pressure Cooling ind Diesel Gener;t:r Av;ilability 3/4.5.F B 3/4.5 CORE AND CONTAINMENT COOLING SYSTEMS energizing the safety bus associated with the inoperable EDG. Within l

one hour of demonstrating SBO-DG operability and once every eight hours thereafter, the normal breaker configuration for energizing the safety bus associated with the inoperable EDG should be verified.

The SBO-DG is a non safety-related, manually started,2000KW generator and is not a qualified replacement for an EDG.

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

3/4.5.G. Deleted Amendment No. 83/4.5-23 i

. LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTEM B. Operation with inoperable Eauipment A. Auxiliary Electrical Eauipment 4

Whenever the reactor is in Run Mode or Startup Mode with the reactor not in a 3 Emergency 4160V Buses AS-A6 .

Cold Condition, the availability of electric Degraded Voltage Annunciation power shall be as specified in 3.9.B.1, System.

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

a. ,Once each operating cycle,
1. From and after the date that calibrate the alarm sensor, incoming poweris not available from the startup or shutdown b. Once each 31 days perform transformer, continued reactor a channel functional test on operation is permissible under this the alarm system, condition for:
c. In the event the alarm system
a. 3 days with the startup is determined inoperable transformer inoperable under 3.b above, commence logging safety related bus or voltage every 30 minutes
b. 7 days with the shutdown until such time as the alarm is transformer inoperable restored to operable status.

During this period, both diesel 4. RPS Electrical Protection generators and associated Assemblies 1 emergency buses must remain operable, a. Each pair of redundant RPS EPAs shall be determined to

2. From and after the date that be operable at least once per incoming power is not available 6 months by performance of from both startup and shutdown an instrument functional test.

transformers, continued operation is permissible, provided both diesel b. Once per 18 months each generators and associated pair of redundant RPS EPAs

  • emergency buses are remain . shall be determined to be operable, all core and containment operable by performance of cooling systems are operable, an instrument calibration and reactor powerlevelis reduced to by verifying tripping of the 25% of design and the NRC is circuit breakers upon the notified within one (1) hour as simulated conditions for required by 10CFR50.72. automatic actuation of the protective relays within the
3. From and after the date that one of following limits:

the diesel generators or associated emergency bus is made or found Overvoltage 5132 volts  ;

to be inoperable for any reason, Undervoltage 2108 volts continued reactor operation is Underfrequency 257Hz permissible in accordance with Specifications 3.4.B.1,3.5.F.1, 3.7.B.1.c, 3.7.B.1.e, 3.7.B.2.c, and .

3.7.B.2.e if Specification 3.9.A.1 and 3.9.A.2.a are satisfied. I Revision 3/4.9-4

. Amendment No. 88,127,145,151 170

.- LIMITING QONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS

  • ' ^ ~

3.9 AUXILIARY ELECTRICAL SYSTEM '4.9 AUXILIARY ELECTRICAL SYSTEM B. Operation with Inoperable Eauioment A. Auxiliary Electrical Eauipment -

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 made or found to j be inoperable for any reason, j continued reactor operation is l permissible for;
a. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, provided the startup transformer and both offsite 345kV transmission lines are available and capable of automatically supplying auxiliary power to the emergency 4160 volt buses, 0.1

^

b.' 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, provided the 23kV transmission line and l

associated shutdown transformer is available and

- capable of automatically supplying auxiliary power to the emergency 4160 volt buses

5. From and after the date that one of the 125 or 250 volt battery systems is made or found to be inoperable ,

for any reason, continued reactor i operation is permissible during the succeeding three days within electrical safety considerations, provided repair work is initiated in l the most expeditious manner to retum the failed component to an operable state, and Specification  !

3.5.F is satisfied.

6. With the emergency bus voltage less than 3958.5V but above 3878.7V (excluding transients) during normal operation, transfer the safety related buses to the diesel generators. if grid voltage continues to degrade be in at least Hot Shutdown within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and in Cold Shutdown within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> unless the grid conditions improve.

Revision 3/4.9-5 Amendment No. 42,61,88,120,127,151