ML20216B628
| ML20216B628 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 02/24/1998 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20216B625 | List: |
| References | |
| NUDOCS 9803130133 | |
| Download: ML20216B628 (3) | |
Text
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SAFETY EVALUATION BY THE OFFICE OF NUCI FAR REACTOR REGULATF.9 RELATED TO AMENDMENT NO.121 TO FACILITY OPERATING LICENSE NO. NPF-30 L
UNION ELECTRIC COMPANY i
CAI i AWAY PLANT. UNIT 1 DOCKET NO. 50-483 l
1.0 INTRODUCTION
- By letter dated August 8,1997, Union Electric Company (the licensee) requested changes to the Technical Specifications (Appendix A to Facility Operating License No. NPF-30) for the Callaway Plant. The proposed changes would revise the Technical Specification (TS) to remove the requirement that Surveillance Requirements 4.7.4.b and 4.7.4.c associated with testing of the essential service water (ESW) are performed while the plant is shutdown.
i0 BACKGROUND The Callaway Plant ESW system consists of two separate 100 percent capacity, safety related, cooling water trains. Each train consists of a self cleaning strainer, prelube tank, one 100 percent capacity pump, piping, valving and associated instrumentation. The pumps automatically start on receipt of a safety injection signal, low suction pressure to the auxiliary feedwater pumps (AFW) or loss of offsite power, at which time system valves are aligned to their required post-accident positions. The ESW system provides a heat sink for the removal of process and operating heat from safety related components during a design basis accident or transient. During normal operation and shutdown conditions the system provides cooling for various safety and non-safety related components. The system also provides emergency makeup to the spent fuel pool and component cooling water system and is the backup source of water to the AFW system.
TS Surveillance Requirement 4.7.4.b.1 requires that the ESW loops shall be demonstrated operable at least once every 18 months during shutdown, by verifying that each automatic
- valve servicing safety-related equipment or isolating the non-nuclear safety-related portion of the system actuates to its correct position on a loss-of-power or safety injection test signal and a simulated high differential pressure test signal. TS Surveillance Requirement 4.7.4.b.2 requires that the ESW loops shall be damonstrated operable at least once every 18 months during shutdown by verifying that each ESW pump starts automatically on a safety injection, low suction pressure (AFW pumps) and loss-of-power signal. TS Surveillance Requirement 4.7.4.c requires that the ESW loops shall be demonstrated operable at least once every 18 9903130133 990224 PDR ADOCK 05000483 i
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I months during shutdown by performing a channel calibration of the differential pressure instrumentation for automatic isolation of the ESW air compressors.
I 3.0 EVALUATION 1
Surveillance activities in accordance with TS 4.7.4.b and 4.7.4.c to demonstrate operability of l
the ESW system are currently required to be performed every 18 months during shutdown.
The licensee is requesting to revise the TS surveillance requirements to delete the requirement to perform the ESW system testing that is required to be performed every 18 months during shutdown. This would allow testing of the valve and pumps online. However, the portion of the surveillance testing verifying the ESW system pump start on a low suction pressure t' the o
AFW pump would still be required to be performed with the plant shutdown due to test conditions rendering all AFW pumps inoperable.
The licensee considers testing of portions of the ESW system online acceptable because the l
. test procedure noes not involve the potential for damage to any plant equipment, the tsst procedures mirtimize the potential for accidentally tripping the plant, and the provisions for on-line testing mirtimize the complication of the actuation circuits so their reliability is not minimized.
The licensee determined that performance of the applicable surveillance requirements at power does not impact the functionality of the ESW system or components, During quarterly performance of the emergency safety feature actuation system (ESFAS) test to satisfy TS i
4.3.2.1, the safety injection (SI) actuation function of many of the automatic valves are tested.
The licensee credits this test as satisfying the requirements of TS 4.7.4.b.1 for the aff.ected valves. The remainder of the required valve tests are performed while shutdown or on an individual component level. Using this method to perform the required valve testing minimizes the potential for an unplanned transient at power. The licensee has determined that the criteria described above being used to detem,be if online testing is acceptable have been satisfied for I
the portions of TS Surveillance Requirements 4.7.4.b.2 and 4.7.4.c to be performed online. TS Surveillance Requirement ' 4.7.4.b.2, low suction pressure to the AFW pumps, will continue to be performed during shutdown.
The licensee has determined that the proposed change to the TS surveillance requirements L
does not have an adverse effect on the impact or the consequences of an accident and does not alter the design assumptions of system and components being used to mitigate the i
consequences of an accxient. Because the surveillance requirements will continue to be performed on er 18-month frequency, no design basis accident will be affected by this change, and the design aM operation of the system will not change. The safety functions or reliability i
of related structures, systems or components will not change, and the possibility of inducing plant transients will not be increased.
Surveillance testing of the AFW system is required every 18 months by the current TSs. The i
requested change to allow online testing of the system valves and pump start features of the ESW system does not change the required surveillance frequency or effect plant safety or 1
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- j. l reliability. The staff, therefore, finds the requested change to TS Surveillance Requirements l
4.7.4.b and 4.7.4.c acceptable.
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4.0 STATE CONSULTATION
In accordance with the Commission's regulation
'M Missouri State Official was notified of the proposed issuance of the amendment. The St' o Jficial had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
l The amendment changes surveillance requirements. The NRC staff has determined that the i
amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (62 FR 66143). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(g). Pursuant to 10 CFR 51.22(b) no c'wironmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment, i
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by.
operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
l Principal Contributor: B. Westreich Date:
February 24, 1998 1
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