ML20079B137
| ML20079B137 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 06/10/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20079B136 | List: |
| References | |
| NUDOCS 9106140005 | |
| Download: ML20079B137 (4) | |
Text
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UNITED STATES 3
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SAFETY EVALUAT10tl EY THE OFFICE Of t;UCLEAR PEACTOR REGULAT10fi f.E!b,T,Ep,,Tp, pp,Eppp,Ep,T, pp,,134,, Jp, f,A,CJ!.J,Ty, pf,Epp,TJy,G,,LJ,C,EN5E NO. DPR-53 At 0 Al'Ef1014EllT NO. 134 TO FACILITY OPERATil!G LICEllSE f10. DPR-69 BALTit40RE GAS AND ELECTRIC C0tPAtlY C A L V E RT C L 1((,5, p u,CL,E,AR, [0,W E R, f,L Ap,T,,,,Up l T, p05. J,, App, 2 p,0,C3E,T,N05_._ 50-317 AND 50-318 1.0 JtgRODUCTION By letter dated June 16, 1986, as supplemented on December 4, 1989, the Baltimore Gas and Electric Company (tlie licensee) submitted a request for changes to the Calvert Cliffs Nuclear Power Plant, Unit Nos. I and 2, Technical Specifications (TS). The first change would modify TS 4.6.P.1.a.? which requires verification that the valves in the Conteinment Spray System flow path are positioned to take suction from the refueling water tank upon receipt of a containment pressure high test signal. The change excludes those valves in the flow path which are locked, sealed, or otherwise secured in position from the verific-+. ion requirement. The second change modifies TS 4.7.11.1.2.c which provides surveillance requirements to demonstrate the operability of the fire pump diesel engine.
The change rer. oves the requirement to perform the surveillar e when the reactors are shut down, thus allowing the surveillance to be performed in the specified time interval regardless of the operating status of the reactor units.
The licensee's June 16, 1988, submittal requested five specific TS changes.
This safety ev'.luation only addressees change request numbers 4 and 5 as described above. The other three requests have been previously acted upon.
The December 4.1989, submittal provided a copy of the procedure used by the licensee to provide the administretive control requirements for locked valves and was included in our initial no significant hazards consideration determination.
2.0 EVALUATION The current TSs require that all the valves in the Containment Spray System flow path be veriried to be in position to take suction from the refueling water tank upon receipt of a containment pressure high signal to assure operability. The requested change will exclude those valves which are locked, sealed, or otherwise secured in position.
The licensee indicated, and we verified, that valves which are locked sealed or otherwise secured in position are already excludad from the verification requirement for the Emergency Core Cooling System, Component Cooling Water System, Service Water System, and the Salt Water System.
9106140005 910610 PDR ADOCK 03000317 F,
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.. The licensee provided a copy of the procedure used to define the administrative controls required for locked valves.
The procedure provides:
the criteria for locking valves; the acceptable methods used to lock valves; tagging requirements; surveillance requirements; and record keeping requirements.
The procedure, Calvert Cliffs Instruction 309B Locked Valves, would be applicable to the Containment Spray System valves which would be excluded from the current TS requirement to verify their position at least once every 31 days.
We have determined that the exclusion of those valves which are locked, sealed, or otherwise secured in position from the surveillance requirement of TS 4.6.2.1.a.2 is acceptable.
This change will make the surveillance requirements for the Containment Spray System consistent with the other safety-related systems identified above and administrative controls for the locked valves are included in the Calvert Cliffs Instruction 3098 to provide reasonable assurance the valves will be properly positioned.
The second request is to delete the requirement that the 18-month surveillance test on the fire pump's diesel engine be done only when the units are shutdown.
The licensee noted that the shutdown conflicts with the current 24-month refueling cycles and would require a dual unit outage since the diesel-driven 2500 gpm fire pump is shared between both units.
A redundant 2500 gpm fire pump is also shared by both units and is electrically-driven to provide diversity.
Additionally, the fire main distribution system has the capability to place back-up fire pumps on the system to establish the necessary redundancy during periods of extended maintenance on any of the primary fire equipment.
The two back-up pumps, one electrically-driven ano one diesel-drivt.n, are each rated at 1500 gpm.
They are both placed in-service when any of the primary pumps are taken out-of-service.
The licensee further indicates that administrative controls are in place to ensure that preventive maintenance is not simultaneously performed on both the primary and back-up pumps.
The flow from one back-up pump can meet the design flow requirements of the fire suppression system.
We have determined that deleting the requirement of TS 4.7.11.1.2.c to perform the 18-month surveillance tests on the diesel-driven fire pump only when the units are shut down is acceptable.
ThL determination is based on the design of the fire suppression system, as discussed above, and greater risk of a fire when the units are shut down and the conflicting 18-month shutdown requirement with the current 24-month fuel cycles.
As noted in the licensee's request, electrical work, welding, testing, and the use of combustibles) periods (i.e.,
the type of activities and materials being uted during shutdown increases the t
likelihood of a fire, l
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3 3.0 STATE C0tlSULTAT10tl In accordance with the Commission's regulations, the Maryland State official was notified of the proposed issuance of the arnendments. The State official had no corcents.
4.0 E t:V I R0f[E t!T AL 00t(S 1,DE,R,AT,10[
The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20, anc' changes to surveillance requirements. The t1RC staff has determined that the amendments involve 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 Comission has previously issued a propowd finding that the amendments involve no G gnificant hazards consideration, and tSere has been no public coment on such finding (55 FR 2431). Accordingly, the amendments meet the eli forth in 10 CFR 51.22(c)(9)gibility criteria for categorical exclusion set Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
5.0 C014CLUS10f4 The Comission 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 amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
D. Mcdonald Date: June 10, 1991 i
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' Mr. G. C. Creel
-2 Jura 10,1991 A copy of the related Safety Evaluation is enclosed.
A Notice of 1ssuance will be included in the Commission's next regular biweetly Federal Register notice.
Sincerely, ogigt:UJ. 51Gl4ED BY8 l
Daniel G. Mcdonald, Senior Project Itanager Project Directorate 1 1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Enclosures:
i 1.
Amendment flo.154 to DPR-53 2.
Amendment No.134 to DPR.69 3.
Safety Evaluation cc w/ enclosures:
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