ML20029E612
| ML20029E612 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 05/11/1994 |
| From: | Wang A Office of Nuclear Reactor Regulation |
| To: | Opeka J CONNECTICUT YANKEE ATOMIC POWER CO. |
| References | |
| REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR TAC-M69450, NUDOCS 9405190170 | |
| Download: ML20029E612 (6) | |
Text
.
- A May 11, 1994 i
Docket No. 50-213 Distribution:
Docket File NRC & Local PDRs PD I-4 Plant SVarga Mr. John F. Opeka JCalvo Executive Vice President, Nuclear SNorris Connecticut Yankee Atomic Power Company AWang Northeast Nuclear Energy Company ACRS (10)
Post Office Box 270 JRogge, RGI Hartford, Connecticut 06141-0270 OGC
Dear Mr. Opeka:
SUBJECT:
HADDAM NECK PLANT - REQUEST FOR ADDITIONAL INFORMATION (TAC N0 M69450)
By letter dated January 13, 1994, Connecticut Yankee Atomic Power Company provided the plant specific summary report in response to the unresolved safety issue (USI) A-46 program at the Haddam Neck Plant.
The staff has reviewed the summary report and determined that additional information is necessary to complete our review of your A-46 response.
Enclosed are questions regarding the A-46 summary report for your facility.
Please respond within 30 days of receipt of this letter.
This requirement af fectr. 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:
See next page 9405190170 940511 e
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Ng May 11, 1994 Docket No. 50-213 Distribution:
Docket File NRC & Local PDRs PD I-4 Plant SVarga Mr. John F. Opeka JCalvo Executive Vice President, Nuclear SNorris Connecticut Yankee Atomic Power Company AWang Northeast Nuclear Energy Company ACRS (10)
Post Office Box 270 JRogge, RGI Hartford, Connecticut 06141-0270 OGC
Dear Mr. Opeka:
SUBJECT:
HADDAM NECK PLANT - REQUEST FOR ADDITIONAL INFORMATION (TAC NO. M69450)
By letter dated January 13, 1994, Connecticut Yankee Atomic Power Company provided the plant specific summary report in response to the unresolved safety issue (USI) A-46 program at the Haddam Neck Plant.
The staff has reviewed the summary report end determined that additional information is necessary to complete our review of your A-46 response.
Enclosed are questions regarding the A-46 summary report for your facility.
Please respond within 30 days of receipt of this letter.
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:
See next page OFFICE LA:PDI-4 PM:PDI-4 D:JDI-4,
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,< j May 11, 1994 Docket No. 50-213 Mr. John F. Opeka Executive Vice President Nuclear, Connecticut Yankee Atomic Power Company Northeast Nuclear Energy Company Post Office Box 270 Hartford, Connecticut 06141-0270
Dear Mr. Opeka:
SUBJECT:
HADDAM NECK PLANT - REQUEST FOR ADDITIONAL INFORMATION (TAC NO. M69450)
By letter dated January 13, 1994, Connecticut Yankee Atomic Power Company provided the plant specific summary report in response to the unresolved safety issue (USI) A-46 program at the Haddam Neck Plant.
The staff has reviewed the summary report and determined that additional information is necessary to complete our review of your A-46 response.
Enclosed are questions regarding the A-46 summary report for your facility.
Please respond within 30 days of receipt of this letter.
This requirement affects one respondent and, therefore, is not subject to Office of Management and Budget review under P.L.96-511.
Sincerely, YGA
/
t Alan B. Wang, Project Manager Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
Request for Additional Information cc w/ enclosure:
See next page l
f Mr. John F. Opeka Haddam Neck Plant Northeast Nuclear Energy Company cc:
Gerald Garfield, Esquire R. M. Kacich, Director Day, Berry and Howard Nuclear Planning, Licensing & Budgeting Counselors at Law Northeast Utilities Service Company City Place Post Office Box 270 Hartford, Connecticut 06103-3499 Hartford, Connecticut 06141-0270 J. M. Solymossy, Director S. E. Scace, Vice President Nuclear Quality and Assessment Services Nuclear Operations Services Northeast Utilities Service Company Northeast Utilities Service Company Post Office Box 270 Post Office Box 270 Hartford, Connecticut 06141-0270 Hartford, Connecticut 06141-0270 Kevin T. A. McCarthy, Director Regional Administrator Monitoring and Radiation Division Region 1 Department of Environmental Protection U.S. Nuclear Regulatory Commission 79 Elm Street 475 Allendale Road Hartford, Connecticut 06106-5127 King of Pressia, Pennsylvania 19406 Allan Johanson, Assistant Director Board of Selectmen Office of 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 J. P. Stetz, Vice President c/o U.S. Nuclear Regulatory Commission Haddam Neck Plant 361 Injun Hollow Road Connecticut Yankee Atomic Power Company East Hampton, Connecticut 06424-3099 362 Injun Hollow Road East Hampton, Connecticut 06424-3099 Nicholas S. Reynolds Winston & Strawn J. J. LaPlatney 1400 L Street, NW Haddam Neck Unit Director Washington, DC 20005-3502 Connecticut Yankee Atomic Power Company 362 Injun Hollow Road East Hampton, Connecticut 06424-3099 Donald B. Miller, Jr.
Senior Vice President Millstone Station Northeast Nuclear Energy Company Post Office Box 128 Waterford, Connecticut 06385 i
j j
f RE0 VEST FOR ADDITIONAL INFORMATION HADDAM NECK PLANT USI A-46
Reference:
1.
Letter from A. Wang (NRC) to J. Opeka Connecticut Yankee Atomic Power Company (CYAPCO), " Safety Evaluation of the Haddam Neck Plant - 120 Day Response," Dated Nov. 25, 1993.
2.
Letter from CYAPC0 to NRC with a Summary Report and Attachments, Dated Jan. 13, 1994.
1.
The safe-shutdown earthquake (SSE) ground response spectra and the approach for developing in-structure spectra were accepted by the staff in Ref. 1.
Provide comparisons of demand-capacity spectra at the top-floor level in the containment and at control room location.
2.
For the evaluation of the large flat bottom vertical tanks, CYAPC0 indicates that their consultants have used the guidelines given in Electric Power Research Institute (EPRI) NP-6041, " Nuclear Powe Plant Seismic Margin." For the resolution of unresolved safety issue (USI) A-46 (i.e., USI A-40), the acceptance criteria in the EPRI report are not acceptable, as they are meant to be used with the margin studies. The 1
staff considers the generic implementation procedure (GIP) guidelines as appropriate for the resolution of USI A-46 and USI A-40.
Provide revised calculations demonstrating the adequacy of the condensate storage tank (CST) and the refueling water storage tank (RWST).
Provide calculations demonstrating the adequacy of the ring-type foundation of the CST.
3.
Provide a summary of the implemented corrections recommended by the peer review group (Attachment D-Reference 2).
4.
Provide a summary of the outliers identified during the review of the raceways in Reference 5.3.7 (Attachment 3-Reference 2).
Are the weights of the fire-barriers properly considered in the seismic adequacy calculations of the raceways?
5.
It appears that CYAPC0 has used.03g as the peak ground acceleration for defining an Operating Basis Earthquake (OBE).
Does the plant safety procedure commit to shutdown the plant when an earthquake event exceeds the OBE?
6.
CYAPC0's January 13, 1994, submittal indicated that there were no significant deviations from GIP-2.
The staff considers the use of the criteria in EPRI Report NP-6041 for evaluating tanks, in lieu of the GIP-2 criteria, a significant deviation.
In light of this, provide confirmation that your USI A-46 implementation program contains no other significant or programmatic deviations from the Seismic Qualification Utilities Group (SQUG) commitments and the gcidance sections of GIP-2.
N T 7.
Describe the extent to which operator action was credited for resolving potential relay chatter issues (e.g., number of instances in which operator action is relied upon, required effort for the operators to perform system resets, and the time constraints for which operators will need to perform system resets).
8.
Identify which outliers will be resolved during the upcoming refueling outage and describe the method of resolution, and identify which outliers will be resolved via the integrated safety assessment program.