ML17037B522

Letter Requesting a Review of All RCS Pressure Boundary Piping and Fitting Material, Including Weld Metal, at the Facility to Determine If It Meets Material Selection and Processing Guidelines

ML17037B522
Person / Time
Site:	Nine Mile Point
Issue date:	09/16/1977
From:	Lear G Office of Nuclear Reactor Regulation
To:	Rhode G Niagara Mohawk Power Corp
References
NUREG-0313
Download: ML17037B522 (7)

Text

SEP 1 6 1977 Docket No. 50-220-Nfagara Mohawk Poorer Corporation ATTN: IIr.,Gerald K. Rhode Vice Pr esident - Engineering 300 Erie Boulevard West Syracuse, Hew York 13202 Gentlemen:

RE: NINE I'/ILE POIN NUCLEAR STATION UNIT NO 1 Boiling Hater Reactor (BWR) operating history indicates that Type 304 and 316 austenitic stainless steel piping in the reactor coolant system (RCS) pressure boundary are susceptible to str ess corrosion cracking.

This is particularly true far "service sensitive" lines; i.e., those that are subject to high stress or that contain relatively stagnant fnterofttent, or low flow fluids. Although stress corrosion cracking is unlikely to cause a rapidly propaoating pipe failure, the presence of such cracks constitutes a degradation of the RCS boundary, and thus js undesirable free a safety standpoint. Therefore, position that steps should be taken to mfnfnfze stress corrosion cracking it is the NRC staff's in BHR piping systems to elfnfnate Chfs condition and to improve overall plant reliability. The details of the staff's posf tfon are contained in the enclosed NURE8-0313, NTechnfcal Repor t on the YIaterial Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping", dated July, 1977.

Me request that you review all of the RCS pressure boundary piping and fitting naterial, including veld metal, at your facility,to detemfne if it meets the naterfal selection and processing guidelines set forth in the enclosed report. You should identify to us any materials that do not meet these guidelines and proprose appropriate changes to your Technical Specifications to incorporate the augmented fnservice inspection requirements speciffed in Section III of the enclosed report. In the case of "service sensitive" lines you should also provide your plans and schedule for the replacement, to the extent practicable, of non-conforming materials with those that conform to the staff's guidelines.

In addition, if you find that you have any pr essure boundary piping that does not confom to the staff's guidelines, ve request that you propose changes to the RCS leakage lfnits and surveillance requirements contained in your Technical Specifications, to bring them into conforoance with the enclosed mode'I Technical Specifications.

OPPICSW SVRNAMSW NRC FORM,518 (9-76) NRCM 0240 N UI d, OOVSRNMSNT PRINTINO OPPICSI ISTS SSIM24

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Niagara ttohawk Power Corporation - 2-You should complete all of the above actions within 90 days. If you have any questions, please contact us.

Sincerely, ppg<nal s>gned by George Lear, Chief Operating Reactors Branch N Di vision of Operating Reactors

Enclosures:

1. "Technical Report on Haterial Selection and Processing Guidelines for BUR Coolant Pressure Boundary Piping"

2. tiodel Tecfinical Speci fications cc w/encl osures:

See next, page DISTRIBUTION:

Docket NRC PDR Local PDR ORB83 Rdg GLear CParrish SNowicki JWetmore OELD OI8IE (3)

DEisenhut TBAbernathy JRBuchanan ACRS (16)

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DATE~ 9/ J 6 /.7.7...9/.........,....../.77.....-...

NRC FORM 318 (9-76) NRCM 0240 k UI S 4OVERNMENT PRINTIN4 OFFICEI ISTO 02~23

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Niagara t1ohawk Power Corporation cc: Eugene B. Thomas, Jr., Esquire LeBoeuf, Lamb, Leiby 5 t1acRae 1757 t1 Street, H. 1!.

Washington, D. C. 20036 Anthony Z. Roisman, Esquire Sheldon, Harmon and Roisman 1025 15th Street, 4'. ll.

5th Floor Washington, D. C. 20005 Oswego City Library 46 .E. Bridge..Street.

Oswego, New York 13126

MODEL TECHNICAL SPEC IF ICATIO REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.X Reactor coolant system leakage shall be limited to:

a. No PRFSSURE BOUNDARY LEAKAGE.

b g GPM UNIDENTIFIED LEAKAGE

c. 2 GPH increase in UNIDENTIFIED LEAKAGE within any 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> period.

d. 20 GPV. IDFNTIFIED LEAKAGE.

APPLICABILITY: Average Coolant Temperature > 212'F.

ACTION:

a. llith any PRESSURE BOUNDARY LEAKAGE, be in at least HOT SHUTDOWN within 12 hours and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. With any reactor coolant system leakage greater than any one of the limits specified in b or d above, reduce the leakage rate to within the limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c. With any increase in UNIDENTIFIED LEAKAGE of > 2 GP<'1 within a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per iod, identi fy the source of leakage within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT. SHUTDOWN wi thin the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN wi thin the fol lowing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.4.X The reactor coolant system leakaoe shall be demonstrated to be wi thin 'each of the above imi ts by:

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a. Monitoring the primary containment sump level and flow rates at le<",st once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b. !monitoring the pr imary contairment atmospheric particu',ate raoioactivity at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

c. (Specify appropriate surveillance tests depending upon the type of leakage detection system utilized).

510DEL TECHNICAL SPEC IF ICATIONS DEFINITIONS IDENTIFIED LEAKAGE

1. XX IDENTIFIED LEAKAGE shall be:

a. Leakage into collection systems, such as pump seal or valve packing leaks, that is captured and conducted to a sump or collecting tank, or

b. Leakage into the containment atmosphere from sources that is both specifically located and known either not to interfere with the operation of the leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE.

. PRESSURE BOUNDARY LEAKAGE 1.XX PRESSURE BOUNDARY LEAKAGE shall be leakage through a non-isolable fault in a reactor coolant system component body, pipe wall or vessel wall..

UNIDENTIFIED LEAKAGE 1.XX UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE.