ML20034G676
| ML20034G676 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 03/04/1993 |
| From: | Link B WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20034G677 | List: |
| References | |
| CON-NRC-93-035, CON-NRC-93-35, RTR-NUREG-1431 VPNPD-93-059, VPNPD-93-59, NUDOCS 9303110005 | |
| Download: ML20034G676 (2) | |
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Electnc POWER COMPANY 231 W Michgort PO. Box 2046. MiNeukee, WI 53201 (414) 221-234S' VPNPD 05 9 -
NRC 0 35 i
March 4,.1993 I
l Document Control Desk U.S. NUCLEAR REGULATORY COMMISSION Mail Station P1-137:
Washington, DC 20555 i.
Gentlemen:
. DOCKETS 50-266 AND550-301 MODIFICATION TO' TECHNICAL SPECIFICATION CHANGE REOUEST 149 MAIN STEAM SYSTEM VALVE TESTING-AND OPERABILITY l
' POINT BEACH NUCLEAR PLANT. UNITS 1 AND 2.
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By letter.dsted February 21,.1992,. as-modified. April 16, 1992,.
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Wisconsin Electric Power Company, Licensee for Point: Beach Nuclear Plant, Units 1:and 2, requested amendments to Facility Operating Licenses DPR-24 and'DPR-27, respectively.- The proposed amendments
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would incorporate and clarify. limiting = conditions for operation (LCOs) and surveillance requirementstforfthe mainisteam.stop valves (MSSVs) and main steam non-return: check, valves ~(NRCVs) incour Tech-1 nical Specifications.
Upon. review of our application.asimodified, j
we have concluded that additional clarification'is required.
Proposed Specification 15.3.4.D would: allow 4 power operation.-to
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continue for up._to four hours with an inoperable MSSV'or NRCV.
If-the valve is not returned.tofancoperable status within.thatLtime, then.the affected.u' nit must:be placed.in hotfshutdowntwithin thef j
next six hours.,As.initiallyLproposed, operation;in: hot shutdown would-be. allowed'to continue provided'the inoperableivalveLremains closed.
However, an inoperableLvalve may.be opened for testing.
-Modifications.were-performed onfthe-Unit'l MSSVsiduringLthe) spring.
~1992-maintenance and refueling outage.
Post-modification _ testing with.the main steam' system' ands valvesLcold,Jindicated.thelvalves were operable.
During.the subsequent-start-up, withjthe. main /steami system at normal' operating 1 temperatures,-.testingLwasfagain.per-:
! formed; One. valve. failed to cycle completelyEclosed. ;A decision-
--was madeEto shut down and cool downLthe' unit toLtroubleshoot and:
affect repairs. ;We determined.that'under.the specification as proposed, repairs would_be delayed if=an: inoperable valve could not Lbe openedfduring the cooldown.-
- If.an'inoperablefvalveiremains closed.during the unit'Lcooldown, additional time'will.belrequiredifor.the valve.to coo 11sufficiently
ifor work'a an.to5be performed. ; Heat;will be dissipatedifrom the' valve l
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Documant Control Dnsk March 4, 1993 Page 2
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body and internals, in this instance, through heat losses to ambient.
If steam is passed through the valve during the cooldown of the unit, the steam cools the valve body and internals, thereby shortening the period of time until the valve is sufficiently cool to allow troubleshooting and repair.
Therefore, we request the last sentence of proposed Specifica-tion 15.3.4.D be modified to state, "An inoperable main steam stop valve or non-return check valve may, however, be opened in the hot shutdown condition to cool down the affected unit and to perform testing to confirm operability."
A Technical Specification page with the proposed specification, as modified by this submittal, is attached.
The Standard Technical Specifications (STS) for Westinghouse reactors, NUREG-1431, Revision 0, requires placing a reactor in hot shutdown (350*F2Tavg2200*F) if an inoperable MSSV cannot be shut and allows continued operation in this mode with the MSIV open.
In this mode of operation, cooling to the reactor core is normally provided by the residual heat removal system.
The energy available for release from a steam generator is low.
The proposed PBNP Specification will allow opening of an MSSV or NRCV when shutdown with Tavg2200'F for testing and to facilitate cooldown.
This is consistent with the action requirements of the STS.
We have reviewed the no significant hazards determination included as Attachment 1 to our February 21, 1992, submittal and have con-cluded that the determination of no significant hazards is appli-cable to our proposed amendment as modified April 16, 1992 and by this letter.
If you have any question or desire additional information, please contact us.
Sincerely, h kit g
Bob Link Subscribed and sworn to before me Vice President this
'/ 4 day of Ma rek
, 1993.
Nuclear Power TGM/jg M
a Oh 6 Not ryVPublic, State of Wisconsin Attachment My commission expires I # ~ 2 h 76.
cc:
NRC Regional Administrator, RIII NRC Resident Inspector Mr.
L.
L.
Smith, PSCW
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