ML20064G228
| ML20064G228 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/18/1978 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20064G218 | List: |
| References | |
| NUDOCS 7812080029 | |
| Download: ML20064G228 (2) | |
Text
..
SAFETY EVALUATIION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 6 TO NPF-6 I
ARKANSAS POWER AND LIGHT COMPANY DOCKET NO. 50-368 INTRODUCTION By letter dated November 13, 1979 the licensee requested one-time relief from Technical Specification (T.S.) 3.8.1.1.b for Arkansas Nuclear One, Unit 2 (ANO-2) to allow operation in Modes 3 and 4 with one diesel generator-and two offsite power sources operable before repairs are completed on the second diesel generator which experienced mechanical failure on November 9, 1978. In addition, the licensee sucmitted in a letter dated November 15 & 17, 1978, proposed Technical Specification changes needed in the limiting conditions of operation (Section 3.8.1.1) and surveillance
(
requirements (Section 4.8.1.1.2) in order to operate as requested.
DISCUSSION AND EVALUATION The licensee states that the relief from the Technical Specification 3.8.1.1.b'as noted above will have no effect on the health and safety of the public since the ANO-2 reactor has not yet been critical. There-fare, there is no decay heat to remove from the core and no safety significance when returning to a heated up condition in the presently authorized Modes 3 and 4 from a cold shutdown condition.-
We have reviewed and evaluated the licensee's requests and evaluation.
We agree with the licensee that the plant can operate safely with only one diesel generator and two offsite power sources until the repairs have been completed on the second diesel generator so that both diesel generators are operational subject to interim changes to the Technical Specifications noted below. The revised Technical Specification require-C ments expire when the Commission has made written determination that both diesel generators are operational, but not later than three weeks from the date of issuance of this license amendment. Our conclusica is based on:
1.
The ANO-2 reactor has not yet been critical and therefore contains j
no fission product sources requiring decay heat removal from the reactor core.
2.
Interim changes to the Technical Specifications during the relief perf01 shall require that the licensee shall:
a.
Verify at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> that the reactor coolant system boron concentration is equal to or greater than 1731 parts per-million.
7 812 0 8 0 0cM
i,
-b.
Secure all deboration paths. In addition during the time of repairs verify the lineups at least once per eight hours, Verify that all control element assemblies not being actively c.
l tested are fully inserted and deenergized.
In addition during the time of relief the control element assemblies not being
,3 actively tested shall be verified to be fully inserted and s
deenergized at least once per eight hours.
ENVIRONMENTAL CONSIDERATION We have determined that the amendment does not authorize a change in effl Jent types or total amounts nor an increase in power level and will not result in any significant environmental impact. Having made this determination, we have further concluded that the amendment involves an action which is insignificant from the standpoint of environmental
(
impact and, pursuant to 10 CFR QSt.5(d)(4), that an environmental impact and/or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of this amendment.
CONCLUSION We have concluded, based on the considerations discussed above, that (1) because the amendment does not involve a significant increase in the probability or consequences of accidents previously considered or a significant decrease in any safety margin, it does not involve a sig-nificant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Commission's regulations ar.d the issuance of this amendment will not be inimical to the common defense and security or to the heath and safety of the public.
(-
Drfenalr4 mad br John F. Stolz, Chief Light Water Reactors Branch No.1 Division of Project Management Dated: 18 November 1978 4
-e
,,,