ML20140C379
| ML20140C379 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/14/1984 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Counsil W NORTHEAST NUCLEAR ENERGY CO. |
| Shared Package | |
| ML20140C384 | List: |
| References | |
| GL-84-09, GL-84-9, LS5-84-6-27, LSO5-84-06-027, LSO5-84-6-27, NUDOCS 8406190337 | |
| Download: ML20140C379 (6) | |
Text
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UNITED STATES g
8 NUCLEAR REGULATORY COMMISSION o
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WASHINGTON, D. C. 20555 k*****p#
June 14, 1984 i
Docket No. 50-245
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L505-84-06-027 l
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Mr. W. G. Counsil, Vice President Nuclear Engineering and Operations Northeast Nuclear Energy Company
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1 Post Office Box 270 Hartford, Connecticut 06141
Dear Mr. Counsil:
SUBJECT:
RELOAD 9 Re:
Millstone Nuclear Power Station, Unit No. 1 The Commission has issued the enclosed Amendmein No'. 98 ~to Provi~si3mfT -
Operating License No. DPR-21 for Millstone Nuclear Power Station., Unit No. 1.
This amendment is in response to your application dated April 9, 1984, as supplemented by errata sheet dated Kar-15,1984; We have comp 1_eted our review of eight of the ten items included-in your application an5"the related proposed Technical Specification changes.
One of_the items, item 10 of attachment-4 to your April 9,1984 submittal was only a draft of your intended technical specification changes related to degraded grid voltage.
We have nevertheless completed our Safety Evaluation of the design and l
included it in the attached SER. But since you have not finalized the proposed technical specification changes we have not approved changes at this time. Also we were unable to complete our evaluation of item 6 because of the extensive on going evaluation of single loop operation and the i
interface with your proposal.
We understand that neither of these items is required for Millstone Unit No.1 startup following the plant outage for Reload 9.
Except for these two items, we have completed our safety evaluation of the Technical Specification changes you have proposed.
We have completed our evaluation of your and the BWR Owners Group's position with respect to the need for recombiners.
Our conclusions and requirements in this regard, presented in Generic Letter 84-09 dated May 8,1984, do not affect the schedule for returning Millstone Nuclear Power Station Unit-1 to normal power operation for fuel cycle 10 following reload-9.
We note that during the reload-9 outage that began in mid April 1984 all recirculation piping welds susceptable to intergranular stress corrosion cracking, IGSCC, (total of 94 welds in 28,22, and 12 inch piping) and i
connecting piping systems (isolation condenser-45 welds, core spray-15 welds, i
low pressure coolant injection-11 welds, shutdown cooling-2 welds, re-l 8406190337 840614
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Mr. W. G. Counsil June 14, 1984 circulation water clean up - 41 welds) were inspected using accepted ultrasonic techniques and the more advanced ultrasonic data recording and processing system (UDRPS) or, where possible dye penetrant.
Repairs by weld overlay or pipe replacement were made as necessary.
The amendment approves Appendix A Technical Specifications related to eight of the items you have identified and allows return to full power operation following the ninth refueling outage.
A Notice of Consideration of Issuance of Amendment to License and Proposed No Significant Hazards Consideration Determination and Opportunity for Hearing related to the requested action was published in the Federal Register on September 21, 1983 (48 FR 43140) for the Reactor Protection System Power Supply and May 30, 1984 (49 FR 22579) for the Reload 9/ Cycle 10 submittal. No request for hearing and no comments were received.
Copies of our related Safety Evaluation Report and the Notice of Issuance are also enclosed. The action will appear in the Federal Register.
Sincerely, Original signed by James Lyons for Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing
Enclosures:
1.
Amendment No. 98 to License No. DPR-21 2.
Safety Evaluation
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e Mr. W. G. Counsil cc Gerald Garfield, Esquire Arthur Heubner, Director Day, Berry & Howard Radiation Control Unit Counselors at Law Department of Environmental One Constitution Plaza Protection Hartford, Connecticut 06103 State Office Building Hartford, Connecticut 06115 John F. Opeka Vice President, Nuclear Operations Northeast Utilities Service Company Post Office Box 270 Hartford, Connecticut 06141 State of Connecticut Office of Policy and Management ATTN:
Under Secretary Energy Division 80 Washington Street Hartford, Connecticut 06115 U.S. Environmental Protection Agency Region I Office ATTN:
Regional Radiation Representative JFK Federal Building Boston, Massachusetts 02203 j?4e--
y Dr. Thomas E. Murley, Regional Administrator Nuclear Regulatory Commission, Region I 631 Park Avenue i
King of Prussia, Pennsylvania 19406 Northeast Nuclear Energy Company ATTN:
Superintendent l
Millstone Plant P. O. Box 128 Waterford, Connecticut 06358 Resident Inspector ~
c/o U.S. NRC Millstone Plant P. O. Box 811 Niantic, Connecticut 06357 i
First Selectman of the Town of Waterford Hall of Records 200 Boston Post Road Waterford, Connecticut 06385
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Mr. W. G. Counsil circulation water clean up - 41 welds) were inspected using accepted ultrasonic techniques and the more advanced ultrasonic data recording and processing system (UDRPS) or, where possible dye penetrant.
Repairs by weld overlay or pipe replacement were made as necessary.
. The amendment approves Appendix A Technical Specifications related to eight of.the items you have identified and allows return to full power operation following the ninth refueling outage.
A Notice of Consideration of Issuance of Amendment to License and Proposed 4
No Significant Hazards Consideration Determination and Opportunity for Hearing related to the requested action was published in the Federal Register on September 21, 1983 (48 FR 43140) for the Reactor Protection System Power Supply and May 30, 1984 (49 FR 22579) for the Reload 9/ Cycle 10 submittal. No request for hearing and no comments were received.
Copies of our related Safety Evaluation Report and the Notice of Issuance are also enclosed. The action will appear in the Federal Register.
Sincerely, Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing
Enclosures:
1.
Amendment No.
to License No. DPR-21 2.
Safety Evaluation cc w/ enclosures:
See next page DISTRIBUTION Docket File NRC PDR Local PDR NSIC ORB #5 Reading DCrutchfield LA JShea OELD ELJordan JMTaylor LJHarmon ACRS (10)
TBarnhart (4)
RDiggs WJones DL: ORB #5 DL: ORB #5 OELD DL:
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Mr. W. G. Counsil circulation water clean up - 41 welds) were inspected using accepted ultrasonic techniques and the more advanced ultrasonic data recording and processing system (UDRPS) or, where possible dye penetrant.
Repairs by weld overlay or pipe replacement were made as necessary.
t I
The amendment approves Appendix A Technical Specifications related to eight of the.itnes you have identified and allows return to full power operation following the ninth refueling outage.
A Notice of Consideration of Issuance of Amendment to License and Proposed No Significant Hazards Consideration Determination and Opportunity for Hearing related to the requested action was published in the Federal Register on September 21, 1983 (48 FR 43140) for the Reactor Protection System Power Supply and May 30,1984 (49 FR 22579) for the Reload 9/ Cycle 10 submittal. No request for hearing and no comments were received.
i Copies of our related Safety Evaluation Report and the Notice of Issuance are also enclosed. The action will appear in the Federal Register.
Sincerely, Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing
Enclosures:
- 1. -Amendment No.
to License No. DPR-21 2.
Safety Evaluation cc w/ enclosures:
See next page i
' DISTRIBUTION Docket File NRC PDR
~;
Local PDR NSIC ORB #5 Reading DCrutchfield LA JShea OELD ELJordan JMTaylor LJHarmon ACRS(10)
TBarnhart(4)
RDiggs WJones
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t Mr. W. G. Counsil June 14, 1984 circulation water clean up - 41 welds) were inspected using accepted ultrasonic techniques and the more advanced ultrasonic data recording and processing system (UDRPS) or, where possible dye penetrant.
Repairs by weld overlay or pipe replacement were made as necessary. Details are to be evaluated and reported in a separate SER prior to plant start up for Cycle 10 operation.
- -The-amendment approves Appendix A Technical Specifications related to eight of the items you have identified and allows return to full power operation following the ninth refueling outage.---~---
A Notice of Consideration of Issuance of Amendment to License and Proposed No Significant Hazards Consideration Determination and Opportunity for Hearing related to the requested action was published in the Federal Register on September 21,1983 (48 FR 43140) for the Reactor Protection System Power Supply and May 30,1984 (49 FR 22579) for the Reload 9/ Cycle 10 submittal. No request for hearing and no comments were received.
Copies of our related Safety Evaluation Report and the Notice of Issuance are
.~ also enclosed.
The action will appear in the Federal Register.
Sincerely, kf16<3 chfield, Chief f,
Denn~s M. Cr pera i q~ ac rs Branch #5
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' is ion-a Licensing
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Enclosures:
1.
Amendment No. 98 to License No. DPR-21 2.
Safety Evaluation cc w/ enclosures:
See next page I
. _ _