ML20027E700

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Proposed Revision to Tech Specs Re Core Spray Sys Special Test Exception
ML20027E700
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 11/08/1982
From:
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20027E693 List:
References
NUDOCS 8211150628
Download: ML20027E700 (11)
v • d • e


Text

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ATTACHMENT 1 PROPOSED TECHNICAL SPECIFICATION REVISIONS CORE SPRAY SYSTEM SPECIAL TEST EXCEPTION BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 i

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f~8211150628 - - - - ~

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1 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.9 REFUELING OPERATIONS (Continued) 3/4.9.3 CO NI ROL RO D P0 SIT IO N. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-5

,3/4.9.4 DE CAY T IM E . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-6 "

3/4.9.5 CO MMU N ICAT IO N S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-7 3/4.9.6 CRANE AND HO IST OPERABILITY. . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-8 3/4.9.7 CRANE TRAVEL-SPENE FUEL STORAGE P00L. . . . . . . . . . . . . . . . . . . 3/4 9-9 3/ 4. 9.8 WATER LEVEL-REACr0R VE SSEL. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-10 3/4.9.9 WATER LEVEL-SPENT FUEL STORAGE P00L. . . . . . . . . . . . . . . . . . . . 3/4 9-11 3/4.9.10 CONIROL ROD REMOVAL Single Control Rod Removal. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-12 Multiple Co ntrol Rod Removal . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-14 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY CONIAINMENE INTEGRITY. . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 10-1 3/4.10.2 ROD SEQUENCE CONTROL SYSTEM. . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 10-2 3/4.10.3 SHUTDOWN MARGIN DEMONSTRAT IONS. . . . . . . . . . . . . . . . . . . . . . . . . 3/4 10-3 3/4.10.4 RE CIRCU LAT ION IJ00P S. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 10-4 3/4.10.5 P IANE SERV ICE WATER. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 10-5

, 3/4.10.6 CO RE SPRAY SYST EM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 10-7 l

BRUNSWICK - UNIT 1 IX Amendment No.

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EMERGENCY CORE COOLING SYSTEMS

, SURVEILLANCE REQUIREMENTS (Continued)

2. Verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
c. At least once per 92 days
  • by:

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1. Verifying that each CSS pump can be started from the centrol +.

room and develops a flow of at least 4625 gpm on recircuiation'-

flow against a system head corresponding to a reactor vessel pressure of > 113 psig.

2. Performing a CHANNEL CALIBRATION of the core spray header AP instrumentation (E21-dPIS-N004A,B) and verifying the set point to be 5, 1.5, psid greater than the normal indicated AP.
d. At least once per 18 months by performing a system functional test which includes simulated automatic actuation of the system throughout its emergency operating sequence and verifying that each automatic valve in the flow path actuates to its correct position. Actual injection of coolant into the reactor vessel is excluded from this test.

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  • See Special Test Exception 3.10.6.

l BRUNSWICK - UNIT 1 3/4 5-6 Amendment No.

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SPECIAL TEST EXCEPTIONS 3/4 10.5 -PLANT SERVICE WATER LIMITING CONDITION FOR OPERATION 3.10.5 The service water conventional header required'to be operating per Specification 3.7.1.2 ACTION b.3 may be removed from operation by stopping the pumps to permit isolating and draining the service water nuclear header for maintenance provided that:

a.

The service water conventional headet remains lineduptosuppl'k.

cooling water to the required ECCS loads.

b. The draining / maintenance on the service water nuclear header will not affect the service water conventional system or lineup described in a. above,
c. Average coolant temperature is <100*F and the heatup rate is

,10*F

< per hour. ~~

d. Two dedicated qualified members of the unit operational staff are assigned to initiate the service water convantional header pumps, should any of the following occur:
1. Any event occurs which requires ECCS actuation.
2. Primary ccolant temperature exceeds 180*F.
3. A loss of offsite power occurs.

APPLICABILITY: CONDITIONS 4 and 5 with the nuclear header inoperable.

ACTION:

With the requirements of the above specification not satisfied, as soon as practicable, restore the:

a. Service water conventional header to operating status per the requirements of Specification 3.7.1.2 ACTION b.3, or.
b. Service water nuclear header to OPERABLE status per Specification 3.7.1.2.

SURVEILLANCE REOUIREMENTS 4.10.5 When the service water conventional header is not operating as specified above: l

a. Prior to securing all service water pumps, verify that the service water conventional header is lined up to supply cooling water for ECCS by verifying that each valve servicing safety-related equipment that is not locked in the proper position is administratively ontrolled in the proper position.

BRUNSWICK - UNIT 1 3/4 10-5 Amendment No.

SPECIAL TEST EXCEPTION 3/4 10.6 CORE SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.10.6 The provisions of Technical Specification 4.5.3.1.c.1 may be suspended-if the suppression pool is drained.

APPLICABILITY: CONDITIONS 4 and 5, with the suppression pool to be drained.

. ACTION: '

With the suppression pool restored to se'rvice, perform Surveillance Requirement 4.10.6.2 below.

SURVEILLANCE REQUIREMENTS 4.10.6.1 Perform Surveillance Requirement 4.5.3.1.c.1 within 7 days prior to draining the suppression pool.

4.10.6.2 Perform Surveillance Requirement 4.5.3.1.c.1 within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of restoring the suppression pool to operable status if the suppression pool has been drained per Specification 3.10.6.

BRUNSWICK - UNIT 1 3/4 10-7 Amendment No.

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS SECTION PAGE 3/4.9 REFUELING OPERATIONS (Continued) 3/4.9.2 I NST RU M E NTAT IO N. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-3 3/4.9.3 CO NTRO L RO D P 0 S IT IO N. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-5 .

.3/4.9.4 DE CAY T DIE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-6 '

3/4.9.5 C0m!U N I CAT IO N S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-7 3/4.9.6 CRANE AND HOIST OPERAB ILITY. . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-8 3/4.9.7 CRANE TRAVE L-SPENT FUEL STORAGE P00L. . . . . . . . . . . . . . . . . . . 3/4 9-9 3/4.9.8 WATER LEVE L-REACIOR VE S SEL. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-10 3/4.9.9 WATER LEVEL-SPENT FUEL STORAGE P00L. . . . . . . . . . . . . . . . . . . . 3/4 9-11 3/4.9.10 CONTROL ROD REMOVAL Single Control Rod Removal. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-12 Multiple Control Rod Removal . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-14 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRDIARY CONTAINMENT INTEGRITY. . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 10-1 3/4.10.2 R0D SEQUENCE CONTROL SYSTEM. . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 10-2 3/4.10.3 SnUTDoWN MARGIN DEM0NSIRAT IONS. . . . . . . . . . . . . . . . . . . . . . . . . 3/4 10-3 3/4.10.4 RE CIRCU LAT ION ID0P S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 10-4 3/4.10.5 P LANI S ERV ICE WATER. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 10-5

- 3/4.10.6 CO RE S P RAY SY ST EM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 10-7 l

BRUNSWICK - UNIT 2 IX Amendment No.

EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

2. Verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, scaled, or otherwise secured in position, is in its correct position.
c. At least once per 92 days
  • by:
1. Verifying that each CSS pump can be started from the control 113 psig.
2. Performing a CHANNEL CALIBRATION of the core spray header AP instrumentation (E21-dPIS-N004A,B) and verifying the setpoint to be 5, 1.5, psid greater than the normal indicated AP.
d. At least once per 18 months by performing a system functional test which includes simulated automatic actuation of the system throughout its emergency operating sequence and verifying that each automatic valve in the flow path actuates to its correct position. Actual injection of coolant into the reactor vessel is excluded from this test.

f

  • See Special Test Exception 3.10.6.

BRUNSWICK - UNIT 2 3/4 5-6 Amendment No.

SPECIAL TEST EXCEPTIONS 3/4 10.5 PLANT SERVICE WATER LIMITING CONDITION FOR OPERATION 3.10.5 The service water conventional header required to be operating per Specification 3.7.1.2 ACTION b.3 may be removed from operation by stopping the pumps to permit isolating and draining the service water nuclear header for maintenance provided that:

a.

The service water conventional header remains lined up to supply:'

cooling water to the required ECCS loads.

b. The draining / maintenance on the service water nuclear header will not affect the service water conventional system or lineup described in a. above.
c. Average coolant temperature is <100*F and the heatup rate is

<10*F per hour.

d. Two dedicated qualified members of the unit operational staff are assigned to initiate the service water conventional header pumps, should any of the following occur:
1. Any event occurs which requires ECCS actuation.
2. Primary coolant temperature exceeds 180*F.
3. A loss of offsite power occurs.

APPLICABILITY: CONDITIONS 4 and 5 with the nuclear header inoperable.

ACTION:

With the requirements of the above specification not satisfied, as soon as practicable, restore the:

a. Service water conventional header to operating status per the requirements of Specification 3.7.1.2 ACTION b.3, or
b. Service water nuclear header to OPERABLE status per Specification 3.7.1.2.

SURVEILLANCE REQUIREMENTS 4.10.5 When the service water conventional header is not operating as specified above: l

a. Prior to securing all service water pumps, verify that the service water conventional header is lined up to supply cooling water for ECCS by verifying that each valve servicing safety-related equipment that is not locked in the proper position is administratively controlled in the proper position.

BRUNSWICK - UNIT 2 3/4 10-5 Amendment No.

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SPECIAL TEST EXCEPTION 3/4 10.6 CORE SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.10.6 The provisions of Technical Specification 4.5.3.1.c.1 may be suspended if the suppression pool is drained.

APPLICABILITY: CONDITIONS 4 and 5, with the suppression pool to be drained.

ACTION: . ,,

With the suppression pool restored to service, perform Surveillance Requirement 4.10.6.2 below.

SURVEILLANCE REQUIREMENTS 4.10.6.1 Perform Surveillance Requirement 4.5.3.1.c.1 within 7 days prior to draining the suppression pool.

4.10.6.2 Perform Sur;9111ance Requirement 4.5.3.1.c.1 within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of restoring the suppression pool to operable status if the suppression pool has been drained per Specification 3.10.6.

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l BRUNSWICK - UNIT 2 3/4 10-7 Amendnent No. -

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ATTACHMENT 2 h CORE SPRAY SYSTEM SPECIAL TEST EXCEPTION 5 DISCUSSION OF PROPOSED TECHNICAL SPECIFICATION REVISIONS '

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Surveillance Requirement 4.5.3.1.c.1 requires that a core spray system (CSS) pump flow test be performed at least once per 92 days. The purpose of this

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submittal is to allow, through the incorporation of a new Special Test '

Exception in the Technical Specifications (TS), the CSS to be considered \ 's' operable if the only reason the system would be declared inoperable would be the inability to perform surveillance testing pursuant to Specification x 4.5.3.1.c.1 due to extenuating plant conditions.

s The CSS is divided into two independent subsystems, each with a 100% capacity (see Updated FSAR Figure 6.3.2-4). Technical Specifications allow the core g

spray pumps to take suction from the condensate storage tanks in Conditions 4 and 5; however, a full flow test can only be performed torus-to-torus. \

During the upcoming Brunswick-1 refueling outage, Mark I torus (i.e., '

suppression pool) modifications will be installed which will necessitate the draining of the suppression pool. Concurrent with the suppression pool draining will be a flood-up of the vessel cavity for a routine refueling.

Both suppression pool draining and vessel cavity fill-up are scheduled for week 2 of the outage. A review of the outage schedule has indicated that the suppression pool will still be drained at 92 days following the suppression '

pool draining. Therefore, the requirements of Surveillance Requirement 4.5.3.1.c.1 cannot be fulfilled. A vessel cavity drain is scheduled to occur during week 14 of the outage to facilitate certain in-vessel surveillance and s maintanance activities. The suppression pool fill-up is scheduled to occur between week 17 and week 20, depending on work requirements. Prior to the '

cavity drain during week 14, a plant modification will be performed which will relocate a core spray system vent valve. The performance of Surveillance Requirement 4.5.3.1.c.1 would be required to demonstrate the operability of the CCS upon completion of this plant modification and prior to draining the vessel cavity during week 14 of the outage. However, Mark I torus x modification work, which will be in progress until approximately week 17, will prohibit the performance of Surveillance Requirement 4.5.3.1.c.1 since the full flow test of the CSS can only be performed torus-to-torus as previously noted.

The proposed Special Test Exception will allow the requirements of \

Specification 4.5.3.1.c.1 to be suspended if the suppression pool is drained when in Conditions 4 and 5. The two proposed Surveillance Requirements for .\

the Special Test Exception will require (1) the performance of surveillance L pursuant to Specification 4.5.3.1.c.1 within 7 days prior to draining the suppression pool, and (2) the performance of surveillance pursuant to Specification 4.5.3.1.c.1 within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of restoring the suppression pool to operable status if the torus has been drained per Specification 3.10.6. A review of previous CSS operability testing shows that the systems are extremely reliable, as no failures were identified back to 1978. The instrumentation associated with the actuation and control of the CSS will continue to be tested during the outage per TS requirements.

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}- 4 L II N s Normally, should a single failure occur in one hore spray subsystem, the redundant core' spray subsystem is available to meet all reflood 3

requirements. Redundant systems that'would be available to supply core.

reflood capability include the condensate system, and the service water l' injection system, with a small volume available from the control rod drive system. Normal core cooling during . the outage time period will be provided by both the residual heat removal (RHR) system and the spent fuel pool cooling system. Even though the RHR system is available for core cooling, it is not available as a core reflood system since its only suction is the torus, which will be drained.

Note: A typographical correction is included for Surveillance Requirement

., 4.10.5 on page 3/4 10-5.

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