ML20070N793

Modifies TS Change Request 145,dtd 910530,as Modified on 930507,requesting Amends to License DPR-24 & DPR-27 to Implement LCO & Surveillance Consistent W/Gl 90-06,in Response to NRC Comments.Affected TS Encl

ML20070N793
Person / Time
Site:	Point Beach
Issue date:	04/28/1994
From:	Link B WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20070N795	List: ML20070N793 ML20070N797
References
CON-NRC-94-036, CON-NRC-94-36 GL-90-06, GL-90-6, VPNPD-94-050, VPNPD-94-50, NUDOCS 9405090212
Download: ML20070N793 (3)

Text

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1 Wisconsin Electnc POWER COMPANY

$ 231 W M chgan. PO Box 204c. Muukee. W 53201-2046 (4141221234$

VPNPD 050 10 CFR 50.4 NRC-94-036 10 CFR 50.90 l April 28, 1994 Document Control Desk

U.S. NUCLEAR REGULATORY COMMISSION Mail Station P1-137 Washington, DC 20555 Gentlemen

DOCKETS 50-266 AND 50-301 f MODIFICATION TO TECHNICAL SPECIFICATION CHANGE REOUEST 145 PRESSURIZER PORV AND BLOCK VALVE REOUIREMENTS AND OVERPRESSURE MITIGATING SYSTEM OPERATIONS POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 i

l By letter dated May 30, 1991, as modified on May 7, 1993, Wisconsin

Electric Power Company, Licensee for the Point Beach Nuclear Plant, requested amendments to Facility Operating Licenses DPR-24 and

DPR-27 for Point Beach Nuclear Plant, Units 1 and 2, respectively.

l The purpose of the requested amendments was to implement the Limiting Conditions for Operation (LCO) and surveillances consistent with those outlined in Generic Letter 90-06 for the l Power Operated Relief Valves (PORV) and PORV block valves. We were recently informed by your staff that our submittal did not adequately implement the proposed LCO requirements.

Specifically, we proposed in our May 7, 1993, submittal, an LCO

, that would allow 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> to depressurize and open to contain-ment atmosphere the reactor coolant system when both PORVs are inoperable and required for low-temperature overpressure protection. We requested the longer action time due to our

concerns that eight hours may not be sufficient time to establish an open pathway to the containment atmosphere. The NRC staff, i in Generic Letter 90-06, recommended that the required action be completed within eight hours.

Although we continue to have concerns with the length of time

to accomplish the required action, we have decided to adopt the NRC staff guidance and have modified our proposed Specification

15.3.15.A.2.c accordingly. We have also modified the wording in

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D'ocument Control Desk April 28, 1994 ,

Page 2 l 1

the Specifications in Section 15.3.15 and associated to basis to clarify the required actions when a PORV(s) is found to be ,

inoperable when tred for low-temperature overpressure protection, j 4 i Specifically:

1. Proposed Specification 15.3.15.A.2 Parts a, b, and c have been modified to include action to depressurize and vent the reactor coolant system. Our previous proposal required that l the RCS be depressurized to atmosphere, j Venting was not addressed.

2. Proposed Specification 15.3.15.A.2.c has been modified to require depressurizing and venting the reactor coolant system within eight hours when both PORVs are determined to be inoperable. The eight-hour action conforms to the staff guidance in Generic Letter 90-06.

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

l 3. Proposed Specification 15.3.15.A.3 has been modified to replace "open to atmosphere" with

" vented" and remove other references to

" atmosphere."

j The bases has been modified to replace "open

, to atmosphere" with " vented" consistent with the revised wording of the proposed LCO action statements. Vented is defined in the bases as an opening in the reactor coolant system pressure boundary to containment atmosphere

,4 or the pressurizer relief tank (normal discharge path for the PORVs) with a relieving capability equivalent to a PORV.

These changes are made in response to staff comments as well as i to more closely reflect the staff's guidance provided in Generic  :

Letter 90-06. These changes are consistent with, and do not change i the intent of our previous submittals. Therefore, the safety  ;

4 evaluation and determination >f no significant hazards contained in those submittals adequately address these changes. .

I I

I D'ocument Control Desk l April 28, 1994 i Page 3 l

I A complete copy of the Technical Specification pages with the i changes made by this and previous submittals is attached.

Please contact us if you have any comments or require additional i

i information.

l 1

Sincerely, 1

/

q . -

Bob Link Vice President Nuclear Power {

l TGM/jg )

Attachment cc: NRC Resident Inspector NRC Regional Administrator, Region III i l

1 i

Subscribed and sworn to before me '

this 49 day of %d i

, 1994.

c'N<,~mJ,,,Jieu<l ,

tiotaryjPublic, State of Wisconsin My commission expires __ '~7 lu . l 1

J l

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