ML20148F478

Safety Evaluation Supporting Amend 98 to License DPR-61

ML20148F478
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	01/19/1988
From:	Office of Nuclear Reactor Regulation
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ML20148F403	List: ML20148F399 ML20148F446 ML20148F478 ML20148F541
References
NUDOCS 8801260263
Download: ML20148F478 (6)

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 98TO FACILITY OPERATING LICENSE N0. DPR-61 CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT DOCKET NO. 50-213

1.0 INTRODUCTION

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By letter dated November 24, 1986, the Connecticut Yankee Atomic Power Company (CYAPC0) submitted a request for an amendment to the Facility Operating License No. DPR-61 to extend the expiration date of the license to forty (40) years from the date of issuance of the operating license.

The currently licensed term for the Haddam Neck Plant is 40 years comencing with the issuance of the construction permit (May 26,1964). Accounting for l the time that was required for plant construction, this represents an effective l operating license term of 37 years for the Haddam Neck Plant. This license amendment changes the expiration date for the Haddam Neck Plant Facility Operating License No. OPR-61 from May 26, 2004, to June 29, 2007, which is l forty years from its June 30, 1967, issuance.

2.0 EVALUATION

, Section 103.c of the Atomic Energy Act of 1954 provides that a license is to be issued for a specific period not exceeding 40 years. 10 CFR 50.51 specifies that each license will be issued for a fixed period of time, to be specified in the license, not to exceed 40 years from date of issuance. 10 CFR 50.57 allows the issuance of an operating license pursuant to 10 CFR 50.56 for the period specified in 10 CFR 50.51 after the construction with the construction permit and when other provisions specified in 10 CFR 50.57 are met. The current license tenn for the Haddam Neck operating license comences with issuance of theconstructionpermit(May 26,1964), expiring May 26, 2004. This represents 8801260263 880119 PDR ADOCK 05000213 P PDR

an effective operating license term of thirty-six (36) years, ten (10) months and twenty-six (26) days. Consistent with Section 103.c of the Atomic Energy Act of 1954 and 10 CFR Parts 50.51, 50.56 and 50.57 of the Comission's regulations, the licensee, by its application dated November 24, 1986, seeks extension of the operating license term for the Haddam Neck Plant such that the fixed period of the license would be 40 years from the date of issuance of the operating license.

The licensee's request for extension of the operating license is based on the fact that a 40-year service life was considered during the design and construction of the plant. Although this does not mean that some components will not wear out during the plant lifetime, design features were incorporated which maximize the inspectability of structures, systems and equipment.

Surveillance and maintenance practices which were implemented in accordance with the ASME Code for Inservice Inspection and Inservice Testing of Pumps and Valves and the facility Technical Specifications provide assurance that any unexpected degradation in plant equipment will be identified and corrected.

The specific provisions and requirements for ASME Code testing are set forth in 10 CFR Part 50.55a.

Aging analyses have been performed for all safety-related electrical equipment in accordance with 10 CFR 50.49, "Environmental Qualification of Electrical Equipment Important to Safety for Nuclear Power Plants,"

J identifying qualified lifetimes for this equipment. These lifetimes will

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be incorporated into plant equipment maintenance and replacement practices to ensure that all safety-related electrical equipment romains qualified and available to perform its safety function, regardless of the overall age of the plant. The staff's Safety Evaluation for environmental qualification i

of safety-related electrical equipment was issued in letters dated December 13, 1982, and February 13, 1987. In these safety evaluations, the staff concluded that the licensee had implemented an environmental qualification program meeting the requirements of 10 CFR 50.59.

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i By letters dated January 23, 1986, April 1 and August 21, 1987, the Connecticut Yankee Atomic Power Company, licensee for the Haddam Neck plant, submitted information on the material properties and the fast neutron fluence (E >1.0 MeV) of the reactor pressure vessel in compliance with the require-ments of 10 CFR 50.61. The Haddam Neck analysis of the fast neutron flux at the inside diameter of the pressure vessel was performed using the material properties determined by testing the specimens in surveillance capsule D.

The calculation was perfonned using the 00T 3.5 code with P , S8 approx-1 imations and a non-standard ENDF/8 based cross section set.

The controlling beltline material was identified to be the intermediate -

sIhell longitudinal welds 6-373-A, B and C (Ref. 3). The reference temperature equation specified in 10 CFR 50.61 as applicable for the Haddam Neck plant is:

RT pts = I + M + (-10 + 470 .v uC + 350 x N$)f where:

I = Initial RT NDT = -56*F M = uncertainty margin = 59'F Cu = w/ Copper in long. welds 6-373-A, B, C = 0.22 N9 = w/o Nickel in long welds 6-373-A, B, C = 0.10 f = Peak fluence on long, welds 6-373-A, 8, C for 32 effective full power years in units of 10 19 n/cmr = 7.51 Therefore RT = 3 + 101.1 x 1,72 = 177.25 F.

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. 4 The staff has reviewed the licensee's submittals and has concluded that the controlling material has been properly identified. The justifications given for the copper and nickel contents and the initial RTNDT are acceptable.

For the copper content, reference was made to WCAP-10433, "Determination of the Copper Content of the Longitudinal Weld Seams in the Intermediate Shell Region of the Haddam Neck Reactor Vessel " which was submitted by letter dated February 17, 1984. The uncertainty margin has been derived from consideration of the bases for these values, following the Pressurized Thermal Shock Rule, Section 50.61 of 10 CFR Part 50.

We have reviewed the infomation submitted by the Connecticut Yankee Atomic .

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Power Company, the licensee for the Haddam Neck plant, in accordance with the requirements of 10 CFR 50.61. We find the estimated value of the fast neutron fluence to the pressure vessel to have conservative error margins and thus is acceptable. The value of the RT pts based on this fluence estimate is less than the 10 CFR 50.61 pressurized themal shock screening criterion and is acceptable. The licensee has comitted to update this estimate in the future. In addition, CYAPC0 has committed, as described in a .61|letter dated August 21, 1987]], to upgrade the pressurized thermal shock l

evaluation as part of its planned conversion from stainless steel clad fuel to zircaloy clad fuel.

The staff has reviewed the Safety Evaluations dated June 30, 1967, and July 1, 1971, as well as the Safety Evaluation related to the full Term Operating License Conversion dated December 27, 1974, for operation of the Haddam Neck Plant. The staff has also reviewed the updated Final Safety Analysis Report (UFSAR) for the facility. While several changes have been made to plant design since the original plant construction was completed, such as revisions to the emergency core cooling systems, fuel assembly modifications to resolve fuel identification concerns, and various other less major design changes, each of these changes where ,it involved a safety-related component has been reviewed and approbed by the staff;

1 the details being documented in the staff's related Safety Evaluation.

! Fu'rther, as required by 10 CFR 50.71(e), these changes and their effect on accident analysis, if any, will be routinely updated in the UFSAR. Our review of the stated Safety Evaluations and the UFSAR for the facility has not identified any concerns associated with approval of the proposed amendment to extend the expiration date of the license that are not already addressed by licensee commitments, operating procedures, and license requirements.

The Exclusion Area for the Haddam Neck Plant consists of licensee-owned property such that the outer boundary of the Exclusion Area coincides with .

Ehesiteboundary. The licensee owns all the land within the Exclusion Area and there has been no change in the earlier findings with respect to com-pliance with 10 CFR 100.3. The licensee has the authority to control activities within the Exclusion Area and anticipates no changes to the Exclusion Area boundary during the extended license period. Changes in population within the Low Population Zone, nearest population center distances and 10 mile radius Emergency Planning Zone have been evaluated by the staff and have been found not to be significant for the period of the license extension. The details of the staff's review are contained in the associated Environmental Assessment dated Accordingly, the Comission's conclusions in the June 30, 1967, Safety Evaluation regarding siting criteria for the Haddam Neck Plant are not changed by the proposed license extension and the Haddam Neck Plant site continues to be acceptable.

Based on the above, it is concluded that the extension of the operating license for the Haddam Neck Plant to allow a 40-year service life is consistent with the safety analyses in that all issues associated with plant aging and population changes have already been addressed. Accordingly, the staff finds the proposed extension of the expiration date'of Facility Operating License No. DPR-61 for the Haddam Neck Plant to be acceptable.

1 3.0 EhVIR0h!4 ENTAL C0t!SIDERATIOP

/n Environn.er.tal Assessr ent relattd to this action was issued Noverr,ber 23,19P7. A Notice of Issuance of en Enviror.n. ental Assessrent and finding cf No Significarit Iripact relatirg to the proposed extension of facility Operating License expiration date for the Haddam Neck Plant was published in the Federal, Register,on December 2, 1987 (52FR 45F,P,0).

4.0 _C_OFCLtlSION The staff has concluded, based on the considerations discussed abcVe, .

't hat (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed tranner, and (2) such activities will be ccnducted in con.pliance with the Ccrmiission's regulations and the issuance of this arrendnient will nct be inimical to the connon defense and security or to the health and safety of the public.

l 5.0 ACKNOWLED_GEMENI l

Principal Contributors: J. Minns PRPB, NRR

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C. f' orris ICSB, hRR L. Lois XPSP, NRR F. Akstulewicz, ISAPD, NPR l

Dated: January 19, 1988 l

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