ML19347C652
| ML19347C652 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 12/23/1980 |
| From: | Clayton F ALABAMA POWER CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8101050021 | |
| Download: ML19347C652 (4) | |
Text
s Atbima Power Cornpany 600 North 18th street Post Office Box 2641 Birmingnam. Alabama 35291 Telephone 205 250-1000 m
F. L CLAYTON, JR.
Senior Vice President Alabama Power the southern e'ectnc system December 23, 1980 j
7 Docket No. 50-348
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Director, Nuclear Reactor Regulation b
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U. S. Nuclear Regulatory Comission
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Phillips Building 7920 Norfolk Avenue Bethesda, Maryland 20014 Attention: Mr. S. A. Varga Gentlemen:
Re:
(1) NUREG-0737 transmitted by Mr. D. G. Eisenhut's letter dated October 31, 1980 (2) APCo letter to NRC (F. L. Clayton to S. A. Varga) dated December 9, 1980 (3) APCo letter to NRC (F. L. Clayton to S. A. Varga) dated December 15, 1980 (4) D. G. Eisenhut's letter to All Pressurized Water Reactor Licensees, dated July 2, 1980 JOSEPH M. FARLEY NUCLEAR PLANT - UNIT 1 TECHNICAL SPECIFICATIONS 1
Reference (2) contained Alabama Power Company's commitment to address the new clarification requirements of Reference (1) by January 5, 1980.
Alabama Power Company addressed the Technical Specifications required by Reference (1) for January 1,1981 in Reference (3).
In Reference (4) the NRC requested that Alabama Power Company submit changes and additions to the Technical Specifications to satisfy category "A" items resulting from TMI-2 Lessons Learned. Our letter of August 7,1980 to Mr. D. G. Eisenhut, which was docketed for Unit I and agreed to by the Staff, stated that Alabama Power Company would respond to these specification requirements for Unit 1 af ter Unit 2 received an operating license. Attachment I to this letter is a cross reference between the category "A" model specifi-cation provisions and sections in the existing and proposed December 15, 1980 (Reference 3) Technical Specifications which show compliance with these requirenents.
Reference (4) also requested that the Farley Unit 1 license be amended by adding license conditions related to system integrity, improved iodine
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8101050
Director, Nuclear Reactor Regulation December 23, 1980 U. S. Nuclear Regulatory Commission Page 2 measurements capability, and calculation of subcooling margin. Alabama Power Company concurs with the license condition relating to improved iodine monitoring. The proposed license condition, which is identical to the one in the Unit 2 license, is included as Attachment 2.
In our judgement, a license amendment is not required for the leakage from systems outside containment program and the backup method for determining subcooling margin.
The bases for this position is as follows:
(1) A proposed technical specification, Section 3.4.6.3, related to leakage outside the containment was submitted by Alabama Power Company in Reference (3). 'This specification limited the allow-able leakage for the systems that could carry radioactive fluids outside containment following an accident and required leak test requirements at least once per 18 months.
(2) The backup method for determining subcooling margin is described in the plant emergency operating procedures, which have been reviewed by and concurred with by the NRC Staff. The licensed operators' training program includes instructions for determining the subcooling margin utilizing the backup method described in the emergency operating procedures.
Alabama Power Company wishes to call your attention to our request for a 90-day grace period described in Reference (3). A grace period of 90 days is requested for the Lessons Learned category "A" items identified in Attachment i from the date of NRC issuance of these changes due to time required to write procedures and train personnel, etc.
If there are any questions, please advise.
)
Yours very tr y l
( F. L. Clayton, Jr.
BDM:de
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cc: ftr. R. A. Thomas Mr. G. F. Trowbridge Mr. L. L. Kintner fir. W. H. Bradford
TMI - LESSONS LEARNED CATEGORY A ITEMS Note: Unless identified by an asterisk, tne APCo Technical Specification listed is the current NRC issued Unit 1 Technical Specification.
Model Technical Specifications.
APCo Technical Specification Identified in Enclosure 1 to
- - Denotes Technical Specification Reference 4 submitted in Reference 3 1.
3.4.4 1.
3.4.4*
2.
3.4.3 2.
3.8.2.3 (Power supply for PORVs) 3.4.4.a*
3.8.2.1 (Power supply for PORV Block Valves) 3.
Table 4.3-7 3.
Table 4.3-7 4.
Table 3.3-3 Item 3 4.
Table 3.3-3 Item 3 5.
Table 3.3-4 Item 3 5.
Table 3.3-4 Item 3 6.
Table 4.3-2 Item 3 6.
Table 4.3-2 Item 3 7.
Table 3.6-1 7.
Table 3.6-1 8.
Table 3.3-3 Item 6 8.
Table 3.3-3 Item 6, 3.7.1.2 9.
Table 3.3-4 Item 6 9.
Table 3.3-4 Item 6, 3.7.1.2
- 10. Table 4.3-2 Item 6
- 10. Table 4.3-2 Item 6
- 11. Table 3.3-5
- 11. Table 3.3-5 12.
3.7.1.2 12.
3.7.1.2
- 13. Table 3.3-10
- 13. Table 3.3-11*, 3.8.2.1 (Power supply for the pressure level transmitters)
- 14. Table 6.2-1
- 14. Table 6.2-l*, 6.2.4.1*
15.
6.3.1 15.
6.3.1*, 6.2.4*
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Alabama Power Company shall provide equipment, training and procedures for accurately determining the airborne iodine concentration throughout the plant under accident conditions.
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