ML20215D077
| ML20215D077 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 09/30/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20215D067 | List: |
| References | |
| NUDOCS 8610100632 | |
| Download: ML20215D077 (3) | |
Text
e eMatuq#g UNITED STATES g
p, NUCLEAR REGULATORY COMMISSION 5
- j WASHINGTON, D. C. 20555
...../
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 13T0 FACILITY OPERATING LICENSE NPF-35 AND AMENDMENT NO. 5 TO FACILITY OPERATING LICENSE NPF-52 CATAWBA NUCLEAR STATION, UNITS 1 AND 2 DUKE POWER COMPANY, ET AL.
INTRODUCTION By letter dated September 10, 1985, Duke Power Company, et al., (the licensee) proposed changes to the Technical Specifications (TS) for Catawba Unit.I to lower the Low-Low Reactor Trip Signal for the Steam Generator Level when the reactor is operating above 30% power level. These changes pertain to Unit 1 only. However, because Units 1 and 2 TS are combined in one document, certain non-substantive changes in format with respect to Unit 2 are required.
Supplemental letters dated November 27, 1985, January 7, 1986, and July 31, 1986, provided revision and clarification to the proposed changes requested in the September 13, 1985, letter.
EVALUATION The proposed changes to Tables 2.2-1, 3.3-2, 3.3-4 and 4.3-1 would (1) lower the trip setpoint so that instead of increasing linearly from 17 to 54.9% of span, while the reactor is taken from 30 to 100% of rated thermal power, it would increase linearly from 17 to 40%; (2) decrease the minimum pennitted trip value (including the setpoint tolerance) at 100% power from 53.2 to 38.3%; and (3) increase the allowable response time for the low-low steam generator reactor trip from 2.0 to 3.5 seconds. The above changes are being proposed to prevent unnecessary reactor trips and auxiliary feedwater initiations due to spurious steam generator low-low level signal fluctuations l
near the current programmed setpoint.
To support the above changes, the licensee requested that Westinghouse ana!yze the effect of reduced steam generator inventory on a Feedwater System Pipe Break both with and without offsite power available and on a loss of Non-Emergency AC Power. The Final Safety Analysis Report (FSAR) will be revised to specify a worst case single failure in the auxiliary feedwater system resulting in 491 gpm of auxiliary feedwater delivered to two steam generators. Core residual heat generation was based on ANSI /ANS 5.1-1979, "American National Standard for Decay Heat Power in Light Water Reactors," August 1979. The assumptions of decay heat postulated by the model proposed by the licensee (ANS 5.1-1979) l are acceptable. Using these revised assumptions for residual heat in a reanalysis of affected accidents in Chapter 15 of the FSAR indicates that all applicable safety criteria were met at the revised low-low level setpoint.
Thus, the staff finds that the proposed revisions to the Catawba Unit 1 TS are acceptable.
Furthermore, the proposed revision to the Catawba 1 FSAR is acceptable when 492 gpm on page 15.2-19a is changed to 491 gpm.
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In addition to the setpoint changes, the licensee has added a new filter to the steam generator low-low level channel circuitry to further reduce spurious reactor trips and auxiliary feedwater initiations. The time constant for this filter is adjusted to a value less than or equal to 1.5 seconds. The staff has reviewed the adjustment and finds it acceptable, j
ENVIRONMENTAL CONSIDERATION The amendments involve 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 amendments involve 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 exposures. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there have been no public comments on such finding. Accordingly, the amendments meet the eligibility criteria for categorical exclusion 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 amendments.
CONCLUSION The Commission made a, proposed determination that the amendments involve no significant hazards consideration which was published in the Federal Register (51 FR 30564) on August 27, 1986, and consulted with the State of South Carolina, No public conments were received, and the state of South Carolina did not have any comments.
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 activities will be conducted in compliance with the Commission's regulations and the issuance of the amendments will not be inimical to the common defense and security or-to the health and safety of the public.
Principal Contributors: Kahtan Jabbour, PWR#4/DPWR-A Rudy Karsch, RSB/DPWR-A Dated:
September 30, 1986 l
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Srptember 30, 1986 AMENDMENT NO.13 TO FACILITY OPERATING LICENSE NPF CATAWBA NUCLEAR POWER STATION, UNIT 1
-AMENDMENT NO. 5 TO FACILITY OPERATINC LICENSE NPF CATAWBA NUCLEAR POWER STATION, UNIT 2 DISTRIBUTION: w/ enclosures:
( EEdkMITC7 NRC PDR Local PDR NSIC PRC System PWR#4 R/F B. J. Youngblood K.-Jabbour M. Duncan 0GC/Bethesda R. Diggs, ADM T. Barnhart (8)
E. L. Jordan L. J. Harmon B. Grimes J. Partlow N IS (10)
OPA RKarsch NThompson EButcher i
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