ML20235J016

Forwards Rev to Proposed Tech Spec 3.7.A.4.6 of 861029 Application for Amend to License DPR-44,expediting Testing of drywell-suppression Pool Vacuum Breaker Following Not Fully Seated Indication,Per NRC 870428 Request

ML20235J016
Person / Time
Site:	Peach Bottom
Issue date:	07/07/1987
From:	Gallagher J PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Butler W Office of Nuclear Reactor Regulation
References
NUDOCS 8707150359
Download: ML20235J016 (4)

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PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 1 1215) S415G)1 l ' "", ,*

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July 7, 1987 MUCLE Am OPanarloNS Docket Nos. 50-277 50-278 Mr. Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555

Subject:

Peach Bottom Atomic Power Station Units 2 and 3 Change to Drywell-Suppression Pool Vacuum Breaker License Amendment Application

Dear Mr. Butler:

The subject License Amendment Application was filed with the Commission on October 29, 1986, requesting revisions to the operability and testing requirements for the Drywell - Suppression Pool Vacuum Breakers to minimized the potential for bypass leakage. By letter dated April 28, 1987, (W. R. Butler, NRC to E. G. Bauer,Jr. PECo) the NRC concluded that the proposed amendment would be acceptable if one revision was made to proposed specification 3.7.A.4.6 on page 170. The revision requested by the NRC would change the action time required for performing a leak test of the vacuum breakers following detection of a "not fully seated" position indication from " perform within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />" to "

initiate within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />".

Licensee concurs with the requested change and hereby amends the April 28, 1987 Application as shown by the vertical bar on revised page 170 enclosed with this submittal. The revision would expedite the testing and verification of vacuum breaker integrity following detection of a "not fully seated" position indication.

Licensee concludes that this proposed revision is bounded by the significant hazards consideration determination and the safety analysis presented in the 87C7150359 DR a707o7 <

ADOCK 05000277 PDR I\

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+ j l -Mr.1 Walter R. Butler, Director Page 2

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October 29, 1986 Application since the revision represents,a i more conservative operabi'lity/ testing restraint from that-

.previously proposed. '

l Should you have any questions or require additional information, please do not hesitate to. contact us.

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Sincerely yours, t

cc: Addressee W.-T.~ Russell, Administrator, Region I, USNRC-T. P.' Johnson,. Resident Site. Inspector j

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i COMMONWEALTH OF PENNSYLVANIA  :

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I COUNTY OF PHILADELPHIA  : l

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i J. W. Gallagher, being.first duly sworn,' deposes and1says: d That he is Vice President of. Philadelphia Electric Company;'

the Licensee herein; that he has read-the. foregoing revision to Licensee's October 29, 1986 Application for Amendment.of Facility Operating Licenses and knows the contents thereof; and that the statements and matters set forth therein are true and correct to  ;)

the best of his knowledge, information and belief.  ;

I h bh C/ O l ,

Vice President 1

i Subscribed and sworn to l

l before me this day of 1987 l

Notary Public 1

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PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.A Primary Containment (Cont'd.) 4.7.A Primary Containment (Cont'd.) l

3. Pressure Suppression Chamber - 3. Pressure Suppression Chamber -  ;

Reactor Building Vacuum Breakers Reactor Building Vacuum Breakers I

a. Except as specified in 3.7.A.3.b a. The pressure suppression chamber-below, two pressure suppression reactor building vacuum breakers chamber-reactor building vacuum and associated instrumentation breakers shall be operable at including setpoint shall be all times when primary contain- checked for proper operation-ment integrity is required. every refueling outage.

The setpoint of the differential i pressure instrumentation which I actuates the pressure suppression chamber-reactor building vacuum breakers shall be 0.5 +/- 0.23 psid.

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b. From and after the date that one I of the pressure suppression chamber-reactor building vacuum breakers is made or found to be inoperable for any reason, reactor operation is permissible only during the succeeding seven days unless such vacuum breaker is sooner made oper-able provided that the repair proce- <

dure does not violate primary I containment integrity.

4. Drywell-Pressure Suppression 4. Drywell-Pressure Suppression i Chamber Vacuum Breakers Chamber Vacuum Breakers

a. When primary containment is a. Each drywell-suppression chamber required, all drywell-suppression vacuum breaker'shall-be chamber vacuum breakers shall exercised through an-opening-be operable and positioned closing cycle once a month.

In the fully closed position (except during testing) except b. When it is determined that as specified in 3.7.A.4.b and a vacuum breaker is inoperable c below. for opening at a time when operability'is required,

b. Drywell-suppression chamber all other operable vacuum breaker vacuum breaker (s) may be shall be exercised immediately "not fully seated" as and every 15 days thereafter shown by position indication until the inoperable if testing confirms that the vacuum breaker has been bypass area is less than or returned to normal service.

equivalent to a one-inch diameter hole. Testing shall be initiated within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> c. Once per operating cycle of initial detection of a each vacuum breaker.shall "not fully seated" position be visually inspected

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