ML17037C439

Letter Requesting Submittal of an Application for License Amendment to Incorporate the Requirements of the Model Technical Specifications

ML17037C439
Person / Time
Site:	Nine Mile Point
Issue date:	09/30/1976
From:	Lear G Office of Nuclear Reactor Regulation
To:	Rhode G Niagara Mohawk Power Corp
References
Download: ML17037C439 (8)

Text

L. l976 SEP 3 0 Distribution Dbcket ORB ¹3 NRC PDR Local PDR VStello .

TJCarter Docket Ho. 50-220 GLear JGuibert SNowicki CParrish Hiagara mohawk Power Corporation Attorney, OELD ATTtl: t1r. Gerald K. Rhode OISE (3)

Vice President - Engineering DE i senhut 300 Erie Boulevard West- TBAbernathy Syracuse, Hew York 13202 JRBuchanan ACRS (16)

Gentlemen:

'E: tlIHE NILE POItlT UHIT HO. 1 In accordance with. the requirements of the tlark I Containment Evaluation Short Term Program (STP), you have recently submitted a Plant Unique Analysis (PUA) of the effects of potential post-LOCA hydrodynamic loads on the suppression chamber (torus) support system and on the piping attached to the torus for your tlark I BWR facility. The hydrodynamic loads which were considered fn your PUA had been adjusted to reflect certain assumed initial conditions for operation of your facility; i.e: operatio'n with a specified differential pressure between the dry-well and the torus, and operation near the rafnimum torus water level allowed by Technical Specifications., Both of these assumptions resu'tt fn a reduction fn post-LOCA hydrodynamic loads on the ttark I Contain-ment structures. Consequently, in order to assure that the PUA results may be conservatively applied to the STP evaluation of your facility's primary containment, the HRC staff has determined that the above-mentioned assumptions utilized in your PUA must be reflected fn the Technical Specifications for your facility.

With respect to drywell-torus differential pressure control assumed fn your PUA, we request that you submit an application for license amendment to incorporate the requfrenents of the enclosed model technical specifications. Your application should include the following support-ing information:

a. A description of the methods used to establish and maintain drywell-torus differential pressure at your facility.

b. 1I description of any system changes or va1ve 1ineop changes~

which are required to implement drywell-torus differentia pressure control.

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c. A description of the insttumentation which you will utilize to monitor the drywell-torus differential pressure. This description should include ( 1) the range and accuracy of the instrumentation, (2 ) the number of instrument channels available, (3) the location of instrument channel readouts, and (4) the Technical Specification requit ements which currently exist for the instrumentation. If Technical Specification requirements do not currently exist for this instrumentation, your application for license amendment should include proposed changes to incorporate appropriate Limiting Cond)tions for Operation and Surveillance Requirements.

With respect to the effects of variations in the torus water level on the PUA results for your facility,ffyou determine that the PUA results are not applicable for the range of torus water levels currently allowed by your Technical Specifications, you must either provide supplemental information

~hich demonstrates that the PUA structural acceptance criteria are met for the currently specified range of torus water levels or submit an application for license amendment to change your Technical Specification limits for torus water level to a range over which the PUA structural acceptance criteria are met. In either case we request that you provide a description of the torus water level instrumentation at your facility. This description should include (1) the range and accuracy of the instrumentation, (2) the number of instrument channels available, (3) the location of instt ument channel readouts, and (4) the Technical Specification requirements which currently exist for the instrumentation. If Technical Specification r'equirements do '-

not currently exist for this instrumentation, your application for license amendment should include proposed changes to incorporate appropriate Limiting Conditions for Operation and Surveillance Requirements.

ate require that the above-mentioned application for license amendment and supporting information be submitted within 30 days of receipt of this letter'.

Three signed otiginals and 40 copies of your response will be required.

This request for generic information was approved by GAO under a blanket clearance number B-180225 (R0072);. this clearance expires July 31, 1977.'incerely, "t j7',

I Original signed bj George Lear, Chief 't Operating Reactors Branch ¹3 Division of Operating Reactors

Enclosure:

tiodel Technical S ecifications oPPIcat9C ~

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Niagara mohawk Power Corpor at)on 3 cc: Arvtn E. Upton, Esquire LeBoeuf, Lamb, Lefby 5 NacRae 1757 N Street, N. M.

Hashfngton, D. C. 20036 Anthony Z. Rodman, Esquire ltownsman, Kessler and Cashdan 1025 15th Street, N. M.

- 5th Floor

'ttashkngton, D. C. 20005 Oswego C)ty Ubrary 120 E. Second Street Os~ego, New York 13126

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RE UIREMENTS

3. 7 CONTAINMENT SYSTEMS 4. 7 CONTAINMENT SYSTEMS Drywell-Suppression Chamber Drywel 1-Suppression Chamber Differential Pressure Di fferential Pressure

.a. Differential pressure a. The pressure differ-between the drywell and ential between the suppression chamber shall drywell and suppression be maintained at equal chamber shall be recorded to or greater than 1.XX at least once each shift.

psid except as specified in (1) and (2) below:

(1) This differential shall be estab-lished within 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> of achieving operating temperature and pressure.

(2) This differential may be decreased to less than 1.XX psid for a maximum of two hours during required operability testing of the HPCI system pump, the RCIC system pump, and the drywell-pressure suppression chamber vacuum breakers.

b. If the differential pressure of specifica-tion 3.7.a cannot be maintained, an orderly shutdown shall be initiated and the reactor shall be in the Hot Shutdown condition within 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> and the Cold Shutdown condition within the following 24 hours1 days <br />0.143 weeks <br />0.0329 months <br />.

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