ML20045F952
| ML20045F952 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 07/06/1993 |
| From: | Wang A Office of Nuclear Reactor Regulation |
| To: | Opeka J CONNECTICUT YANKEE ATOMIC POWER CO., NORTHEAST NUCLEAR ENERGY CO. |
| References | |
| TAC-M86400, NUDOCS 9307090220 | |
| Download: ML20045F952 (4) | |
Text
a July 6, 1993 Docket No. 50-213 DISTRIBUTION:
1 Docket File'-
NRC & Local PDRs PD I-4 Plant SVarga Mr. John F. Opeka JCalvo Executive Vice President SNorris Nuclear Engineering and Operations AWang Connecticut Yankee Atomic Power Company OGC Northeast Nuclear Energy Company ACRS (10)
Post Office Box 270 LTDoerflein, RI Hartford, Connecticut 06141-0270
Dear Mr. Opeka:
SUBJECT:
HADDAM NECK PLANT - ADDITIONAL ATMOSPHERIC STEAM DUMP CAPABILITY, l
REQUEST FOR ADDITIONAL INFORMATION (TAC NO. M86400)
By letter dated May 4,1993, Connecticut Yankee Atomic Power Company submitted s
a proposed Technical Specification change to reflect the replacement of four main safety vah es (one per main steamline) with a new type of Code safety valve which will increase the remote manual atmospheric steam dump capability.
3ased on our review of your submittal, the staff has determined that tdditional information is necessary to complete our review.
Enclosed are additional questions regarding your submittal.
This requirement affects one respondent and, therefore, is not subject to Office of Management and Budget review under P.L.96-511.
Sincerely, Original signed by:
Alan B. Wang, Project Manager Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/ enclosure:
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July 6,1993
. i Docket No. 50-213 Mr. John F. Opeka Executive Vice President Nuclear Engineering and Operations Connecticut Yankee Atomic Power Company Northeast Nuclear Energy Company Post Office Box 270 Hartford, Connecticut 06141-0270 i
Dear Mr. Opeka:
SUBJECT:
HADDAM NECK PLANT - ADDITIONAL ATMOSPHERIC STEAM DUMP CAPABILITY,-
l REQUEST FOR ADDITIONAL INFORMATION (TAC NO. M86400)
By letter dated May 4, 1993, Connecticut Yankee Atomic Power Company submitted a proposed Technical Specification change to reflect the replacement of four main safety valves (one per. main steamline) with a new type of Code safety valve which will increase the remote manual atmospheric steam dump capability.-
Based on our review of your submittal, the staff has determined that j
additional information is necessary to complete our review.
Enclosed are additional questions regarding your submittal.
This requirement affects one respondent and, therefore, is not subject to Office of Management and Budget review under P.L.96-511.
Sincerely, hx Q4t/
i i
Alan B. Wang, Pro ect Manager Li Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
As stated 7
- t CC W/ enclosure
- I See next page s
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Connecticut Yankee Atomic Power Company Haddam Neck Plant j
t CC:
Gerald Garfield, Escuire R. M. Xacich, Director a
Day, Berry and Howard Nuclear Licensing Counselors at Law Northeast Utilities Service Company City P1 ace Post Office _-Box 270-Hartford, Connecticut 06103-3499 Hartford, Connecticut 06141-0270 i
W. D. Romberg, Vice President D. 0. Nordquist Nuclear, Operations Services Director of Quality Services Northeast Utilities Service Company Northeast Utilities Service Company l
Post Office Box 270 Post Office Box 270 i
Hartford, Connecticut 06141-0270 Hartford, Connecticut 06141-0270 Kevin McCarthy, Director Regional Administrator Radiation Control _ Unit Region I i
Department of Environmental Protection U.S. Nuclear Regulatory Commission State Office Building 475 Allendale Road Hartford, Connecticut 06106 King of Prussia, Pennsylvania 19406 Allan Johanson, Assistant Director Board of Selectmen Office' af Policy and Management Town Office Building Policy Development and Planning Division Haddam, Connecticut 06438 80 Washington Street Hartford, Connecticut 06106 Resident Inspector Haddam Neck Plant
-l J. P. Stetz, Vice President c/o U.S. Nuclear Regulatory Commission 1
Haddam Neck Plant 361 Injun Hollow' Road Connecticut Yankee Atomic Power Company East Hampton, Connecticut 06424-3099 362 Injun Hollow Road i
East Hampton, Connecticut 06424-3099 Nicholas S. Reynolds Winston & Strawn 1
G. H. Bouchard, Nuclear Unit Director 1400 L Street, NW j
Haddam Neck Plant Washington, DC 20005-3502 Connecticut Yankee Atomic Power Company
-l7 362 Injun Hollow Road East Hampton, Connecticut 06424-3099 l
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Enclosure RE0 VEST FOR ADDITION L INFORMATION FOR HADDAM NECK PROPOSED REVISION TO TECHNICAL SPECIFICATIONS FOR ADDITIONAL ATMOSPHERIC STEAM DUMP CAPACITY I.
In the May 4, 1993 submittal, it is stated that the four new main steam safety valves can be remotely operated as well as self actuated.
Please provide a description of the proposed valve design and installation describing the overpressure protection operation of the valve and how it would meet the applicable ASME Code provisions affected by the new valve design.
(a)
Which edition of the ASME Code is the design code of record?
(b)
How does the new valve design meet the Code requirements for pilot valves?
(c)
Are stop valves placed upstream of the new safety valve (or the pilot valves), and how does this meet the Code stop valve requirements? Are any stop valves positively controlled and interlocked such that there is no stop valve position resulting in the pilot lines being isolated?
(d)
Does the plant code of record allow crediting of the full capacity of the new valve design?
(e)
Describe the capacity certification testing for the new valves as required by the ASME Code.
2.
Is the design and installation of the remote operator mechanisms such that they could not impede the self actuating function of the valves?
3.
The May 4,1993 submittal states that the capacity of the new valves is not required to provide system overpressure protection. Has the plant overpressure protection analysis been revised to reflect this change to the plant design basis such that the capacity of the new valves is not credited for overpressure protection?
4.
Describe the proposed inservice testing to be performed on the new valves with alternative fluids and how this will meet the ASME Code requirements.
4
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