ML17054B532
| ML17054B532 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 03/27/1985 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | Hooten B NIAGARA MOHAWK POWER CORP. |
| References | |
| NUDOCS 8504080171 | |
| Download: ML17054B532 (12) | |
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Docket No. 50-410 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 MAR 27
]985 Hr. B. G. Hooten Executive Director, Nuclear Operations Niagara Mohawk Power Corporation 300 Erie Boulevard Hest
- Syracuse, New York 13202
Dear Hr. Hnoten:
SUBJECT:
APPLICATION FOR AUTHORIZATION TO UTILIZE AN ALTERNATF. TO THE RE(UIREHENTS OF 10 CFR 50.55a FOR THE NINE MILE POINT NUCLEAR STATION UNIT 2 The staft has completed its review of the Niagara Mohawk Power Corporation (NHPC) application f'r authorization to utilize an alternate to the requirements of 10 CFR 50.55a(c){l).
10 CFR 50.55a(c){1) requires that components which are part of the Reactor Coolant Pressure Boundary (RCPB) meet the requirements for Class 1 components in Section III of the ASME Boiler and Pressure Vessel Code.
10 CFR 50.55a(a)(3) further states that alternates to the requirements of paragraph (c) of this section may be used under certain conditions when authorized by the Director of the Office of Nuclear Reactor Regulation.
NMPC proposes to utilize as a main steam isolation valve (MSIV) a valve that meets all the requirements of the ASHE Code for Section III, Class 1,
components with the exception of paragraph NB-2211.
NB-2211 requires that the material for the tensile and impact test specimens be heat treated in the same manner as the component including an allowance for any subsequent heat treatment.
The one MSIV under consideration is identified as valve 7A and is located outside the primary containment in steam line A.
This 24-inch valve (one of eight) was designed and fabricated by Gulf 8 Western Hanufac-turing Company/Fluid Systems Division (currently Crosby Valve Division of Moorco Company) under their ASME Section III program and Certificate of Authorization and was Code stamped N Class I.
The valve body, which was manufactured by Cameron Iron Works, is a carbon-manganese steel forging con-forming to the requirements of material specification SA 350 Grade LF2.
During a review of documentation on the MSIV's, it was discovered that the material used for the test specimens for valve body 7A was normalized, austenitized and water quenched and then tempered for six hours at 1200'F,
- whereas, the valve body itself was normalized, austenitized and water quenched, tempered for six hours at 1200'F and then subjected to approximately 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> of postweld heat treatment (PWHT) at 1125 F.
Therefore, the requirements of NB-2211 of Section III for Class 1 components have not been met and the body of valve 7A is not in conformance with the ASME Code.
That is, while the heat ssososoan sso>>7
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treatment on the test material specimens and the valve body are identical the test material specimens were not subjected to simulated PWHT as required by the ASME Code.
In order to demonstrate that MSIV 7A is acceptable, an independent metallurgical evaluation was conducted by Dr. R.
D. Stout of Lehigh University to determine the effects of the time at temperature during PWHT.
Although the valve body received approximately 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> of PWHT, the evaluation was performed using 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />, providing the capability of PWHT in the future if needed during plant life.
The evaluation showed that because temperature is the dominant factor, tempering has the major effect on the material properties and that PWHT has a
negligible additional effect.
There would not, therefore, have been a signifi-cant difference in the test results if the test material specimens had been subjected to simulated PWHT.
Since the test values are considerably above the minimum values required by the material specification, this difference would not have caused the values to fall below those of the material specification.
The valve body is, therefore, acceptable.
Actions which could be taken to bring MSIV 7A into total compliance with Section III, Class I, of the ASME Code would result in hardship and unusual difficulty.
These actions are (I) cutting and testing specimens from the valve itself, or (2) complete replacement of the valve body.
Both of these actions involve extensive rework and would not result in a compensating increase in the level of quality and safety of the plant.
Therefore, the NRC staff'inds that MSIV 7A as currently fabricated and installed is acceptable and will provide an acceptable level of safety.
Since MSIV 7A is not in total compliance with Section III of the ASME Code f'r Class 1 components and, therefore, should not have a
Code N-Symbol Stamp or a completed Data Report (Form NPV-1), we require the following actions be implemented by NMPC to reflect the current status of the valve:
(I)
Revise the Design Specification as appropriate.
Advise the manufacturer and the ANI, who signed the Certificate of'ompliance and Certificate of Shop Inspection on the Data Report Form NPV-l, that your findings indicate that the Code Rules have not been met and their records should be so modified.
Annotate the Data Report Form to this effect.
(2)
Remove or deface the Code N-Symbol Stamp on the valve nameplate.
In addition to the above, MS IV Nine Mile Point Unit 2 equality with 10 CFR 50, Appendix 8 for Category A valve in accordance in conformance with Section XI 7A shall remain within the scope of the Assurance Program that is in conformance RCPB components and shall be tested as a
with an Inservice Testing Program that is of the ASME Code.
Sincerely, Harold R. Oenton, Director Office of Nuclear Reactor Regulation
~ ~
In addition to the above, MSIV Nine Mile Point Unit 2 guality with 10 CFR 50, Appendix B for Category A valve in accordance in conformance with Section XI IN
)
7A shall remain within the scope 'of the, Assurance Program that's 'in, conformance RCPB compo'nents and shall, be tested as a
with an Inservice,Testing Program that is of the ASME Code.,
'incer'el@,
, 'nto'i agned,.hy,.
}I..'Dcnton; Harold Ri 'Denton,'irector -: Office of Nuclear-"React'or'Regulation E1 Distribution: NRC P0R Local PDR PRC System NSIC LB82 Reading EHylton EWeinkam Bordenick, OELD ACRS (16) JPartlow BGrimes EJordan FMiraglia ASchwencer MHaughey WJohnston BDLiaw WHazelton DSellers RBosnak HBrammer RKirkwood
- Previous concurrences concurred on by:
- LB82/DL/PM EWeinkam:lb 02/26/85
- OELD Bordenick 03/14/85
- LBg2/DL/BC ASchwencer 02/27/85
- AD/L/DL TNovak 03/05/85 FM for
- D/DL HThompson 03/05/85
- DD/NRR D/
DEisenhut HDe on 03/25/85 03/ 3 /85
I gM ~ ~
In addition to the above, MSIV Nine Mile Point Unit 2 guality with 10 CFR 50, Appendix B for Category A valve in accordance in conformance with Section XI 7A shall remain within the scope of the Assurance Program that is in conformance RCPB components and shall be tested as a with an Inservice Testing Program that is of the ASME Code'. \\ Sincerely, I Origkal Qgned bl H. R. Dentett Harold R. Denton, -Director Office of Nuclear Reactor Regulation Distribution: NRC PDR Local PDR PRC System NSIC LB¹2 Reading EHylton EWeinkam Bordenick, OELD ACRS (16) JPartlow BGrimes EJordan FMiraglia ASchwencer MHaughey WJohnston BDLiaw WHazelton DSellers RBosnak HBrammer RKirkwood
- Previous concurrences concurred on by:
FM for
- D/DL HThompson 03/05/85
- LB¹2/DL/PM EWeinkam:lb 02/26/85
- OELD Bordenick 03/14/85
- LB¹2/DL/BC
- AD/L/DL ASchwencer TNovak 02/27/85 03/05/85
- DD/NRR D/
DEisenhut HDe on 03/25/85 03/p /85
4 'I
Nine Mile Point 2 Mr. B. G. Hooten Executive Director, Nuclear Operations Niagara Mohawk Power Corporation 300 Erie Boulevard West
- Syracuse, New York 13202 CC:
Mr. Troy B. Conner, Jr., Esq. Conner 8 Wetterhahn Suite 1050 1747 Pennsylvania
- Avenue, N.W.
Washington, D.C. 20006 Richard Goldsmith Syracuse University College of Law E. I. White Hall Campus
- Syracuse, New York 12223 Ezra I. Bialik Assistant Attorney General Environmental Protection Bureau New York State Department of Law 2 World Trade Center New York, New York 10047 Resident Inspector Nine Mile Point Nuclear Power Station P. 0. Box 99
- Lycoming, New York 13093 Mr. John W. Keib,: Esq.
Niagara Mohawk Power Corporation 300 Erie Boulevard West Syrac'use,-'New York 13202 .Jay M. Gutierrez,'sq. U. S. Nuclear Regulatory Commission 'egion I >; 631 Park Avenue King of Prussia,'enn'sylvania 19406 Norman Rademacher, Licensin'g Niagara Mohawk Power Corporation -300. Erie Boulevard West Syracuse,-'New York 13202 d d d
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