ML20064D023
| ML20064D023 | |
| Person / Time | |
|---|---|
| Site: | Farley |
| Issue date: | 10/26/1978 |
| From: | Clayton F ALABAMA POWER CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7810310070 | |
| Download: ML20064D023 (2) | |
Text
Alcite3 PC*ff Company 600 North 1' n Street g f Post Omco Boi 2641
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Birminga.am. Aiabama 35291
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Te'epnone 205 323-5341 b
F. L. CLAYTON, JFL Senior vice presics AlabamaPower the southem electnc systern October 26, 1978 Docket No 50-348 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Attention:
Mr. Albert Schwencer
Dear Mr. Schwencer:
PI: Temporary Change to Operating License No. NPF-2 Technical Specifications Alabama Power Company proposed the attached changes to Joseph M.
Farley Nuclear Plant Operating License No. NPF-2 Technical Specifications involving temporary waiver to Technical Specification 3.7.8.1 to add
" Provisions of Specification 3.0.4 are not applicable on a one time' basis commencing 10/26/78 and ending 11/1/78 at 1230 hours0.0142 days <br />0.342 hours <br />0.00203 weeks <br />4.68015e-4 months <br />." This waiver is applicable to the action statement of 3.7.8.1 as relates to surveillance requirement 4.7.8.1.b.2.
The Plant Operations Review Committee and the Nuclear Operations Re-view Board have reviewed the above proposed changes and have determined that the changes do not involve an unreviewed safety question as shown in the attached safety evaluation.
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In accordance with 10 CFR 50.30(c)(1)(1), three signed originals and thirty-seven additional copies of these proposed changes are enclosed.
If you have any questions, please advise.
Yours very truly, F. L. Clayto, Jr.
FLCJr/TNE:bhj 4?;
Enclosures
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Notary Public cc:
Mr. R. A. Thomas 0(
Mr. G. F. Trowbridge 9
7870310070 f
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Safety Evaluation l
Temporary Change to Technical Specification 3.7.8.1 Action Statement 1
Requested One Time Only Change:
Add to Technical Specification 3.7.8.1 Action Statement the following words:
" Provisions of Specification 3.0.4 are not applicable on a one time basis commencing 10/26/78 and ending 11/1/78 at 1230 hours0.0142 days <br />0.342 hours <br />0.00203 weeks <br />4.68015e-4 months <br />."- This waiver is applicable to the action statement of 3.7.8.1 as relates to surveillance requirement 4.7.8.1.b.2.
, Background and Bases:
On 10/25/78 while reviewing test results relative to Surveillance Reqairement 4.7.8.1.b.2 it was noted that the filter penetration for the B Train of the penetration room filtration system was.07% filter penetration versus the
.05% filter penetration requirement of Regulatory Guide 1.52, Rev. 1, July 7, I
1976, paragraph C.5.c.
Based on these results the penetration room filtration system (B Train) was declared inoperable at 1230 hours0.0142 days <br />0.342 hours <br />0.00203 weeks <br />4.68015e-4 months <br />.an 10/25/78. The plant filter testing consultant is scheduled to be on-site 10/27/78 to follow correc-tive maintenance and perform the retest.
On 10/25/73 at 2235 hrs. the unit tripped. The unit is presently in Mode 3 with startup pending resolution of this problem.
The Train B filter penetration is.07% as measured by the DOP test for particu-lates and the Train A filter penetration is.02% for particulates as demon-strated in surveillance tests conducted in September, 1978. The charcoal test (i.e. Freon) was acceptable on both trains.
The penetration room filtration system is only required during the recirculation i
phase after a LOCA.
Repairs to the Train B filters are anticipated to be minor, only requiring adjust-ment of spring tension on the filter banks.
Nd disassembly-is anticipated.
Under these conditions Train B could be placed in service within 20 minutes and hence would be available in the unlikely event of a LOCA.
In view of the fact that Train B can be returned to service prior to being required if Train A experienced failure and Train B is presently capable of 99.93% efficiency the safe opera-tion of Farley Nuclear Plant Unit 1 is assured.
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Conclusion:==
i This change will allow Farley Nuclear Plant Unit 1 to return to power and operate for the remaining period currently allowed by Technical Specification Limiting Condition for Operation 3.7.S.1.
The proposed change does i
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involve an unreviewed safety question as defined by 10CFR50.59.
not 1
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