ML20235G896

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Safety Evaluation Supporting Amend 111 to License DPR-40
ML20235G896
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 09/24/1987
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20235G874 List:
References
GL-84-15, TAC-55860, NUDOCS 8709300280
Download: ML20235G896 (3)


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< SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED T0' AMENDMENT NO.111 TO FACILITY OPERATING LICENSE N0. OPR-40 OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT NO. 1 DOCKET NO. 50-285

1.0 INTRODUCTION

By letter dated March 28, 1986, as supplemented by letters dated April 9, 1986, March 13 and June 22, 1987, Omaha Public Power District (licensee) requested changes to the Technical Specifications for Fort Calhoun Station, Unit 1.

The changes are in response to NRC's July 2, 1984 Generic Letter 84-15 entitled, " Proposed Staff Actions to Improve and Maintain Diesel Generator Reliability." The changes are intended to reduce the number of unnecessary diesel generator cold fast starts, thus making them more reliable.

2.0 EVALUATION The proposed Technical Specifications changes and our evaluation of these proposed changes are as follows.

2.1 Action Statement 2.4 Technical Specification (TS) Section 2.4, Limiting Conditions for Operation (LCO) of the Containment Cooling System, currently allows during power operation a total of two components listed in TS Sections 2.4.1.a and 2.4.1.b to be inoperable at any one time (in addition to one raw water pump) provided that the emergency diesel generator connected to the other engineered safeguards 4.16 kV bus (1A4 or 1AS) is started to demonstrate operability. The licensee has proposed to delete the requirement of testing diesel generator ,

during the LC0 for Containment Cooling System. The staff has reviewed the above proposed TS change and finds it to be consistent with Generic Letter 84-15 to improve and maintain the diesel generator reliability by reducing excessive diesel generator testing and find it acceptable.

2.2 Action Statement 3.7(1)a Technical Specification 3.7(1)a currently requires diesel generator surveillance to be performed from ambient conditions and for the diesel generator to start and accelerate to rated speed and voltage in less than or equal to 10 seconds. The proposed change will require starting each diesel generator at least once per 184 days from ambient e709300280 ADOCK O}ppg$h PDR P

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s-conditions and accelerating to rated speed and voltage in less than or equal to 10 seconds. All other engine starts in this specification may be proceeded by an engine prelube period and/or other warm-up procedures as recommended by the manufacturers. We find this change to be consistent with Generic Letter 84-15 andl acceptable. Other  !'

proposed changes in this TS section are as follows:

Technical Specification 3.7(1)c has been reworded for clarity. Current TS 3.7(1)e becomes 3.7(1)c(iii) and is modified to include verification that the autoconnected loads do not exceed the 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> rating of the engine rather than continuous rating of 2500 kW, consistent with Standard Technical Specifications. The portion of current TS 3.7(1)c ,

. dealing with manual control of the diesel generators and breakers has been separated from TS 3.7(1)c and has been designated as TS 3.7(1)e.

However, the frequency of this requirement was changed from annual to refueling. The licensee also proposed an administrative change to delete the word " satisfactory" from this TS section. In addition, a note has been added to the Basis Section 3.7 to specify that Generic Letter 84-15 recommendations have been incorporated into these TSs.  ;

Based on its review, the staff finds the above changes to be acceptable.

2. 3 Technical Specification 3.1, Instrumentation and Control In order to reduce unnecessary diesel generator starts', the licensee has also proposed a change to TS 3.1. This TS refers to the requirements for surveillance testing in terms of checks, calibration, and testing of the Engineered Safety Features found in Table 3-2. These changes are as follows:

Table 3.2, Item 11 addresses several surveillance requirements for diesel generators that are currently tested as part of the testing of Engineered Safety Feature Instrumentation and Control. Additionally, other diesel generator testing requirements are specified in TS Section 3.7. Some of the diesel generator surveillance requirements of Table 3-2 Item 11 are redundant to surveillance requirements of TS Section 3.7. The licensee has proposed to delete the redundant sur-veillance requirements and move the remaining diesel generator surveillance requirements from Table 3.2 to TS Section 3.7. Speci-fically, requirements of existing Table 3.2, Item 11a will be deleted because it is redundant to the proposed revision to Section 3.7.1.a.

The requirement of Table 3-2, Item lib regarding the start of diesel generator upon a Safety Injection Signal Actuation Test has been deleted {

from the Table because this circuitry is exercised during surveillance requirements of TS 3.7(1)c. The requirement of Table 3-2, Item lle (to perform a test of the diesel generator during refueling) is also f redundant to the proposed revision to TS Section 3.7(1)c. Therefore, the requirement of Item 11c has been deleted. The requirements of (

Table 3-2, Item 11d (to test the diesel generated auto start initiating  !

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circuits prior -to startup) have been moved to the proposed revised TS Section 3.7(1)b. The staff finds the above proposed changes to be consistent with Generic Letter 84-15 and 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 Commission has previously published a proposed finding that the amendment involves no significant hazards consideration and there has been no public .l comment on such finding. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR S51.22(c)(9).

. Pursuant to 10 CFR SSI.22(b), no environmental impact statement or environmental l assessment need be prepared in connection with the issuance of the amendment.

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 activities will be conducted in compliance'with the Commission's regulations, and the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

4 Date: September 24, 1987 Principal Contributor: 0. Chopra 1

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