ML20210A243
| ML20210A243 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 01/29/1987 |
| From: | James Shea Office of Nuclear Reactor Regulation |
| To: | Mroczka E NORTHEAST NUCLEAR ENERGY CO. |
| Shared Package | |
| ML20210A248 | List: |
| References | |
| NUDOCS 8702060439 | |
| Download: ML20210A243 (4) | |
Text
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[ft IECge UNITED STATES j" -
h NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20655 1 ;g January 29, 1987 Dock *et No. 50-245 Mr. Edward J. Mroczka, Senior Vice President Nuclear Engineering and Operations Northeast. Nuclear Energy Company Post Office Box 270 Hartford, Connecticut 06141-0270
Dear Mr. Mroczka:
SUBJECT:
AMENDMENT NO. 1 TO MILLSTONE UNIT 1 TECHNICAL SPECIFICATIONS Re: Millstone Nuclear Power Station, Unit No. 1 The Consnission has issued the enclosed Amendment No. I to Facility Operating License No. DPP.-21 for the Millstone Nuclear Power Station, Unit No. 1.
This amendment is in response to your applications as shown below:
1.
a.
Amendment request letter dated July 9, 1985.
b.
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 August 14, 1985 (50 FR 32791).
hc connents or requests for hearing were received.
This part of the anendn.ent adds new reporting requirements consistent with 10 CFR 50.72 and 10 CFR 50.73.
2.
a.
Anendnent request letters dated October 7 and 16,1985.
b.
Notices of Consideration of Issuance of Amendnent to License and Proposed No Significant Hazards Consideration Determination and Opportunity for Hearing related to the requested action were published in the Federal Register on November 20, 1985 (50 FR 47865/
47866). No comnents or request for hearing were received.
This portion of the amendment:
consolidates Specifications 3.5.F.7 and 3.5.F.8 concerning conditions for work on control rod drive mechanisms and fuel movement and replacement during the refuel condition, into Specification 3.5.F.7 to eliminate redundancy; substitutes, in place of Specifications 3.5.F.7.d and 3.5.F.8.b, a single reworded technical specification, Specification 3.5.F.7.d that requires a 33-foot depth of water in the refueling cavity during refueling, equal to, but in place of, the 383,000 gallons formerly specified. This is a technical specification simplification; B702060439 87012 PDR ADOCK 05000 P
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. modifies low pressure coolant injection and core spray requirements to allow the operator to rack out pump breakers to prevent an inadvertent injection and possible drywell or refuel floor flooding with the reactor in the refuel mode; defines the REFUEL CONDITION, Specification NN, and clarifies operability requirements of various systems during REFUEL AND SHUTDOWN CONDITIONS.
3.
a.
Amendment request letter dated January 10, 1986.
b.
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 March 12, 1986 (51 FR 8598).
No comments or requests for hearing were received.
This section of the amendment adds new sections (3.6.J.3 and 4.6.J.3) to designate the salt-splitting capacity for replacement condensate demineralizer resin. Other word changes are for clarification and consistency with these sections.
The replacement resin is evaluated in accordance with requirements in Regulatory Guide 1.56 for water purity in boiling water reactors.
4.
a.
Amendment request letter dated January 28, 1986.
b.
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 April 23, 1986 (51 FR 15404).
No comments or requests for hearing were received.
This portion of the amendment (1) deletes the requirement for isolation condenser operability during continued power operation whenever offsite 345 kv power is not available, (2) changes the word " operating" to
" operable" in technical specification section 3.9.B.2., (3) renumbers 3.9.B.3 and 3.9.B.4 to 3.9.B.4 and 3.9.B.5, (4) establishes new additional limiting conditions of operation for section 3.9.8.3, and (5) adds a new paragraph to Basis 3.9.8 relating to availability of power from the Reserve Station Service Transformer (RSST).
5.
a.
Amendment request letter dated February 27, 1986.
b.
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 April 23, 1986 (51 FR 15405).
No comments or requests for hearing were received.
I i
4 i
. This part of the amendment clarifies functional testing requirements for the safety / relief valve (SRV) pcsitive indication system by revising technical specifications 4.6.E.4 and 4.6.E.5.
Also included are three pages from the technical specifications that were inadver-tently omitted during the reproduction and distribution of the FTOL package issued on October 31, 1986. Also, minor editorial corrections and text rearrangement for clarity are included.
As described in the enclosed Safety Evaluations, the staff concludes that these changes are acceptable. The Notice of Issuance for this amendment will appear in the Coninission's next biweekly Federal Register notice.
j Sincerely,
/s/
i.
James J. Shea, Project Manager Integrated Safety Assessment Project Directorate Division of PWR Licensing - B
Enclosures:
1 1.
Amendment No. I to License No. DPR-21 l
2.
Safety Evaluation i
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6 This part of the amendment clarifies functional testing requirements for the safety / relief valve (SRV) positive indication system by revising technical specifications 4.6.E.4 and 4.6.E.5.
Also included are three pages from the technical specifications that were inadver-tently omitted during the reproduction and distribution of the FTOL package issued on October 31, 1986. Also, minor editorial corrections and text rearrangement for clarity are included.
As described in the enclosed Safety Evaluations, the staff concludes that these changes are acceptable. The Notice of Issuance for this amendment will appear in the Commission's next biweekly Federal Register notice.
Sincerely, Le C -
p James J. S ea, Proiect Manager Integrated Safety Assessment Pro.iect Directorate Division of PWR Licensing - B
Enclosures:
1.
Amendment No. I to License No. DPR-21 2.
Safety Evaluation cc w/ enclosures:
See next page l
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