ML20215E360
| ML20215E360 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 10/06/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20215E359 | List: |
| References | |
| NUDOCS 8610150252 | |
| Download: ML20215E360 (3) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION n
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 15TO FACILITY OPERATING LICENSE NPF-35 CATAWBA NUCLEAR STATION, UNIT 1 DUKE POWER COMPANY, ET AL.
INTRODUCTION By letter dated June 6,1986, Duke Power Company, et al., (the licensee) pro-posed that License Condition 2.C.(12)(a) of Facility Operating License NPF-35 be amended to (1) allow an extension of time for the resolution of the accumulator i
tank instrumentation issue and (2) update License Condition 2.C.(12)(a) to make it consistent with License Condition 2.C.(8)(a) of Catawba Unit 2 Facility Operating License, NPF-52, issued on May 15, 1986, because the same issue is applicable to both Units. The extension of time would be for two complete cycles of operation.
EVALUATION In NPF-35 issued on January 17, 1985, license condition 2.C.(12)(a) regarding compliance with Regulatory Guide 1.97, Revision 2 stated that:
" Prior to startup following the first refueling outage, Duke Power Company shall implement modifications (installation or upgrade) for those items listed below consistent with the guidance of Regulatory Guide 1.97, Revision 2 unless prior approval of an alternate design of these items is granted by the NRC staff. These items, as listed in Duke Power Company's letter of September 26, 1983, are:
(a) reactor coolant system cold leg water temperature, (b) containment sump water level, (c) residual heat removal heat exchan temperature, (d) accumulator tank level and pressure, (ger outlet e) steam generator pressure, (f) containment sump water temperature, (g) chemical and volume control system makeup flow and letdown flow, (h) emergency ventilation damper position, (1) area radiation, and (j) plant-airborne and area radiation."
The above issue is related to Generic Letter 82-33, Supplement 1 to NUREG-0737, regarding the Requirements for Emergency Response Capabilities.
It was also discussed in Section 7.5.2 of Supplement 4 to the Catawba Safety Evaluation Report (SER). Subsequent licensee submittals and staff reviews, &s documented in Supplement 5 to the Catawba SER issued in February 1986, resolved all the above items except for item (d). Furthemore, the staff slightly modified that item to require the licensee to designate either level or pressurg.as the key variable to be upgraded. This variable is currently under additional staff review and further discussion with the licensee is expected. Assuming'that the licensee plans to upgrade either the accumulator level or pressure instrumen-tation, it is estimated that approximately 23 months lead time would be required for implementation during a refueling outage. This would coincide with the end of the cycle 3 refueling outage currently scheduled to begin in January 1989.
8610150252 861006 DR ADOCK 05000413 PDR
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The primary function of the accumulator pressure or level instrumentation is to monitor the pre-accident status of the accumulators to assure that the passive safety system is in a ready state to serve its safety function. The licensee stated that the accumulator tank level or pressure are not referenced in any emergency procedure covering design basis events which may cause a harsh environment. No operator actions in these procedures are based on accumulator indications. Therefore, the staff concludes that extension of the date for upgrading the accumulator pressure or level instrumentation until startup following the third refueling outage is acceptable.
Based on the above discussion, the modified License Condition 2.C.(12)(a) would state that:
" Prior to startup following the third refueling outage, Duke Power Company shall provide qualified accumulator discharge instrumentation."
ENVIRONMENTAL CONSIDERATION The amendment involves a change in use of facility components located within the restricted area as defined in 10 CFR Part 20 and changes in surveillance requirements. The staff has determined that the amendment involves no signi-ficant 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 in-crease in individual or cumulative occupational exposure. The Comission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there have been no public coninents on such finding.
Accordingly, the amendment meets the eligibility criteria for categorical ex-clusion set forth in 10 CFR Section 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 the amendment.
CONCLUSION The Comission made a proposed detennination th'at the amendment involves no l
significant hazards consideration which was published in the Federal Register (51 FR 28996) on August 13, 1986, and consulted with the state of South Carolina.
i No public coninents were received, and the state of South Carolina did not have j
any coments.
We have concluded, based on the considerations discussed above, that: (1) l there is reasonable assurance that the health and safety (,f the public will j
not be endangered by operation in the proposed manner, and (2) such activities l
will be conducted in compliance with the Coninission's regulations, and the issuance of the amendment will not be inimical to the coninon defense and security or to the health and safety of the public.
l Principal Contributors:
Kahtan Jabbour, PWR#4/DPWR-A James Lazevnick, EICSB/DPWR-A Dated: October 6, 1986 l
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4 Octobtr 6, 1986 AMENDMENT N0.15 TO FACILITY OPERATING LICENSE NPF CATAWBA NUCLEAR POWER STATION, UNIT 1
)ISTRIBITION_: w/ enclosures:
(_ X)cket 'lle)
NRC PDR Local.PDR:
~PWR#4 R/F B. J. Youngblood K. Jabbour M. Duncan OGC/Bethesda R. Diggs, ADM T. Barnhart (4)
E. L. Jordan L. J. Harmon B.. Grimes J. Partlow ACRS (10)
OPA B. Mann N. Thompson E. Butcher J..Lazevnick