B11752, Forwards PWR Safety Relief & Block Valve Adequacy Rept, Per NUREG-0737,Item Ii.D.I.Response Providing Analysis of Effect of as-built Relief & Safety Valve Discharge Piping on Valve Operability Also Encl
| ML20133F390 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 10/01/1985 |
| From: | Opeka J NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20133F393 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM B11752, NUDOCS 8510110009 | |
| Download: ML20133F390 (3) | |
Text
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October 1,1985 Docket No. 50-423 Bil752 Director of Nuclear Reactor Regulation Mr. B. 3. Youngblood, Chief Licensing Branch No. I Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555
References:
(1)
W. G. Counsil letter to B. 3. Youngblood, Transmittal of Response to DRAFT SER open item, dated July 11,1984.
(2)
B. 3. Youngblood letter to W. G. Counsil, SER for Millstone Nuclear Power Station, Unit No. 3, dated July 1984.
Dear Mr. Youngblood:
Millstone Nuclear Power Station, Unit No. 3 Safety, Relief and Block Valve Adequacy Report In accordance with item II.D.1 cf NUREG-0737, Pressurized Water Reacter (PWR) licensees and applicants were required to conduct testing to qualify the reactor coolant system relief and safety valves, block valves, and associated piping and supperts under expected operating conditions for design-basis transients and accidents.
The Electric Power Research Institute (EPRI) was contracted by the PWR Owners Group to develop and carry out a generic test program and to provide the generic test to be used by the PWR utilities to satisfy the requirements of NUREG-0737, Item II.D.I. Testing of valves in the EPRI program was completed by December 31, 1931.
By a letter dated April 1,1982, from D. P. Hoffman, Chairman of the PWR Safety and Relief Valve Test Program Subcommittee, the EPRI/PWR Owners Group transmitted the reports to the NRC.
On the basis of a preliminary review of the EPRI generic reports, the NRC has concluded that the reports contain data that can be used by the applicant to prepare an Item II.D.1 plant-specific response for the valves and associated piping for Millstone Unit No. 3.
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, Section 5.4.13.2 of Millstone Unit No. 3 FSAR stated that the valves indentical to the power-operated relief valves and safety valves at Millstone Unit No. 3 were. tested as a part of EPRI/PWR owners Group Program and Northeast Nuclear Energy Company (NNECO) committed to submit a Millstone Unit No. 3 plant-specific evaluation of this program to the NRC prior to fuel load.
In Reference (1), NNECO committed to submit Millstone Unit No. 3 plant-specific information on block valve operability. Enclosed is a copy of the report "PWR Safety, Relief and Block Valve-Adequacy Report for Millstone Unit No. 3" which provides the above information. In Reference (2), NNECO also committed to submit an analysis of the effect of as-built relief and safety valve discharge piping on valve operability.
Attachment II provides our response.
These
. submittals should resolve the Staff's concerns regarding SER confirmatory item (11).
If there are any questions, please contact our licensing representative directly.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY et. al.
BY NORTHEAST NUCLEAR ENERGY COMPANY Their Agent A F. CLsL
- 3. F. Opekd U
Senior Vice President STATE OF CONNECTICUT )
) ss. Berlin COUNTY OF HARTFORD
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Then personally appeared before me 3. F. Opeka, who being duly sworn, did state that he is Senior Vice President of Northeast Nuclear Energy Company, an Applicant herein, that-he is authorized to execute and file the foregoing information in the name and on behalf of the Applicants herein and that the statements contained in said information are true and correct to the best of his knowledge and belief.
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/) W N Y Notary Publ g Commission Expues Wrch 31,1988
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ATTACHMENTI Millstone Nuclear Power Station, Unit No. 3 PWR Safety, Relief and Block Valve Adequacy Report