ML20210R514
| ML20210R514 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 02/09/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20210R429 | List: |
| References | |
| NUDOCS 8702170430 | |
| Download: ML20210R514 (7) | |
Text
_
p natroq g;
p UNITED STATES g
NUCLEAR REGULATORY COMMISSION y.
g WASHINGTON, D. C. 20555 t
%,...../
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 89 TO FACILITY OPERATING LICENSE NO. DPR-61 CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT DOCKET NO. 50-213 1.0 Introduction By letter dated October 20, 1981, Connecticut Yankee Atomic Power Company (CYAPC0 or the licensee), applied pursuant to 10 CFR 50.90, to modify its operating license, DPR-61, by incorporating revisions into the Haddam Neck Plant Technical Specification (TS).
Item 5 of the licensee's submittal proposes an amendment to TS Section 4.3(A)(2) to delete the requirements for verification that the charging pump is automatically sequenced to start and load onto the emergency diesel generator. The charging pumps are not credited in any safety analyses and, therefore, are removed from the auto-matic diesel loading sequence.
Following discussions with the staff in the summer of 1985, CYAPC0 provided additional material (References 2, 3, 4) in support of the requested change.
Following the review of these documents, the staff, by letter dated July 29, 1986, requested additional information in support of the requested change.
In August of 1986, CYAPC0 provided additional justification (References 1,5,
- 6) for the request to remove the charging pumps from the automatic sequencing requirements of diesel generator testing.
Following the staff review of the additional information, the staff concluded that no additional informa-tion was required to support the licensee's request.
By letter dated October 20, 1981, Connecticut Yankee Atomic Power Company requested seven different license amendments governing the subjects areas of diesel generator testing, degraded grid voltage protection and other 8702170430 870209 PDR ADOCK 05000213 P
' administrative changes (see Federal Register notice, 48 FR 49580, October 26,1983).
Item 1 of the licensee's application was resolved by issuance of Amendment 65 on September 3, 1985.
Items 6 and 7 concerning surveillance requirements on the containment air recirculation system and the emergency diesel generator system will be superseded by the licensee's pending Standard Technical Specification (STS) conversion submittal. Staff review of these requests has been deferred to the pending STS submittal.
Staff review of these requests has been deferred to the pending STS submittal.
Items 2,3 and 4 concerning the degraded grid voltage protection remain un-resolved pending a revised submittal of the specific technical specifica-tions pages.
Item 5 concerning the charging pump surveillance is resolved by the issuance of this amendment.
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 October 26, 1983, (48 FR 49580). No request for hearing and no public comments were received.
2.0 Discussion and Evaluation The staff has previously evaluated in Reference 1 the need for the charging pumps to automatically sequence to the emergency bus. The staff's evaluation addressed the need for boron injection by the charging pumps during post accident conditions in the event of a main steam line break. This concern was resolved by changing the technical specifications to impose a 3% shutdown margin during subcritical operation and imposing a reduction in the trip setpoint to 25% of rated power when the reactor power is less than 10% of rated power. These imposed requirements provided assurance that the reactor would remain subcritical in the post-accident condition. The staff, therefore, concluded in Reference I tha't the charging pumps were not required for automatic sequencing onto the emergency bus.
4
' This technical specification amendment deletes the surveillance require-ment to verify automatic sequencing of the charging pumps. The amendment further provides for verification that the charging pump can be manually started and will attain its required discharge head. This manual verifi-cation will only be done after the automatic sequencing of other pumps to the emergency bus has been completed and one of the safety injection pumps can be secured. Securing the safety injection pump assures that the emergency bus will not become overloaded when the charging pump is placed on line. The surveillance frequency was unchanged.
Based on the above review of the analyses, the staff concludes that the technical specification change proposed by the licensee will provide additional assurance that the emergency bus will not become overloaded and that the Haddam Neck Plant will be operated safely. We therefore conclude that the proposed amendment is acceptable.
3.0 Environmental Consideration This amendment involves a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Connission has previously issued a proposed finding that this amendment involves no significant hazards l
consideration and there has been no public comment on such finding.
Accordingly, this amendment meets the eligibility criteria for cate-gorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
i
s.
. s:
[-
4_
' 4.0 Conclusion We have~ concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner; and
-(2) such activt les will be conducted in compliance with the Comission's regulations and the issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public.
. l' Dated: February 9, 1987 Principal Contributor:
D. L. Caphton, DRS, Region I l
References 1.
Letter:
D. L. Ziemann to W. G. Counsil dated October 24, 1978, forwarding License Amendment No. 29.
2.
Letter:
W. G. Counsil to D. L. Ziemann (NRC) dated September 22, 1978 concerning Emergency Power Systems
-3.
Letter:
D. C. Switzer to Peter A. Morris (NRC) dated December 30, 1971 concerning Emergency Core Cooling Sys em Performance 4.
Letter:
D. C. Switzer to D. J. Sovolt (NRC) dated May 19, 1972 concerning Emergency Core Cooling System Report.
5.
Letter:
W. G. Counsil to D. L. Zieman (NRC) dated May 22, 1978 concerning Emergency Power Systems 6.
Letter:
W. G. Counsil to D. L. Ziemann (NRC) dated May 24, 1978 concerning Technical. Specification Changes for Core Cooling Systems i
k l
l l
i r
i References-1.
Letter:
D. L. Ziemann to W. G. Counsil dated October 24, 1978, forwarding License Amendment No. 29.
2.
Letter:
W. G. Counsil to D. L. Ziemann (NRC) dated September 22, 1978 concerning Emergency Power Systems 3.
Letter:
D. C. Switzer to Peter A. Morris (NRC) dated December concerning Emergency Core Cooling Sys em Performance
, 1971 4.
Letter:
D. C. Switzer to D. J. Sovolt (NRC) dated May 19, 1972 concerning Emergency Core Cooling System Report.
5.
Letter:
W. G. Counsil to D. L. Zieman (NRC) dated May 22, 1978 concerning Emergency Power Systems 6
Letter:
W. G. Counsil to D. L. Ziemann (NRC) dated May 24, 1978 concerning Technical Specification Changes for Core Cooling Systems s
. A copy of our related Safety Evaluation is enclosed. This action will appear in the Commission's biweekly notice publication in the Federal Register.
Sincerely, Francis M. Akstulewicz, Jr Integrated Safety Assessment Project Directorate Division of PWR Licensing - B
Enclosures:
1.
Amendment No. 89 to License No. DPR-61 2.
Safety Evaluation cc w/ enclosures:
See next page DISTRIBUTION
' Docket File a,
OGC-Bethesda
~'
RDiggs TBarnhart (4)
FMiraglia LJHarmon FAkstulewicz WRegan PAnderson WJones 9EEE CMiles, OPA MBoyle AWang kh ISAP:
IS D:ISA g/g k\\ ',
sd CGrimes FAkstulewicz:dj pan etson q/ ?
2/(,/87 1/p/87 1/y1/87 g
2{%7 M9