ML19318A582
| ML19318A582 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/18/1980 |
| From: | Trimble D ARKANSAS POWER & LIGHT CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| 1-060-15, 1-60-15, NUDOCS 8006230401 | |
| Download: ML19318A582 (3) | |
Text
{{#Wiki_filter:_ P3 3 ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 UTTLE ROCK. ARKANSAS 72203 (501)371-4000 June 18, 1980 1-060-15 2-060-21 Director of Nuclear Reictor Regulation ATTN: Mr. Darrell G. disenhut, Acting Director Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Subject:
Arkansas Nuclear One - Units 1 & 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6 Five Additional TMI-2 Related Requirements for Operating Reactors (File: 1510.3, 2-1510.3) Gentlemen: l Your letter of May 7,1980, requested that we make commitments to the subject requirements. Below is our response to each item as it applies to Arkansas Nuclear One - Unit 1 and/or Unit 2. 1.A.1.3. - Shift Manning Your ~etter stated that requirements for the implementation of this item would be provided shortly through separate correspondence. At this time,'we have_not received the requirements for implementation. This item will be addressed, as appropriate, after the requirements for implementation are issued.
- 1. A. 3.1. - Revise Scope and Criteria for Licensing Examinations Your letter stated that requirements for the implementation of this item were provided to us by letter dated March 28, 1980.
We received a letter from Harold R. Denton dated March 22, 1980, on the subject of Qualifications of Reactor Operators. This letter set forth re-vised criteria to be used by the staff in evaluating reactor operator training and licensing, and also provided implementation dates. AP&L is modifying its Reactor Operator training program in order to meet the requirements of the March 22 letter. These requirements will be met by the dates as stated in the March 22 letter. I.C.S. - Procedures for Feedback of Operating Experience to Plant Staff AP&L will review its, procedures and revise them as necessary to assure that operating information pertinent to plant safety is supplied to operators and other personnel and is incorporated into training and retraining programs. The reviews _and procedure modifications should be completed by January 1,.1981. -{0062E 040l usuom =co'ssoum urnmessvsreu e
7 Mr. Darrell G. Eisenhut June 18, 1990 1 II.K.3.1. - Installation and Testing uf Automatic PORV Isolation System ANO-1: NUREG-0660 delays implementation of this item until completion of studies specified in Item II.K.3.2., which should indicate if implementation is necessary. ANO-2:. This item'is not applicable to ANO-2 since it has no PORV. II.K.3.2. - PWR Vendor Report on PORV Failure Reduction ANO-1:.Various actions have alrehdy been taken by AP&L in order to decrease the probability of a small break LOCA caused by a stuck-open PORV. Among these are the addition of a PORV posi-tion _ monitoring device and upgrading of the power supply to the PORV and to the block valve upstream of the PORV. Several options are available for further study. Improvement of the reliability of the present PORV is one of these options. This would be accomplished by cycle testing the PORV and/or key valve parts and would give statistical reliability data to supplement the planned EPRI operability tests. Accomplish-ment of this program is possible by January 1, 1981. Another option is a developmental program to identify, qualify, and test for installation an improved PORV design..This pro-gram would require until mid-1981 to complete. Positive results from either of these programs would negate the need for an automatic PORV isolation system per Item II.K.3.1. ANO-2: This. item is not applicable to ANO-2 since it has no PORV. 'II.K.3.3. - Reporting Safety and Relief Valve Failurer, and Challenges Through conversations with your staff,' AP&L learned that the first annual report would' be required to include only failures / challenges which have occurred to Safety and Relief Valves since April 1,1980. AP&L's posi-tion is that this report should include only failures and challenges to primary system-Safety and Relief Valves. Otherwise, AP&L will be able to meet these requirements by January 1, 1981. II.K.3.5. - Automatic Trip of-Reactor Coolant Pumps During LOCA Study of the criteria' for early Reactor Coolant Pump (RCP) trip will con-tinue. Presently, the1necessary RCP's (i.e., the number consistent with operating ~ guidelines) are being tripped,menually. Upon resolution of the issue as to when and how to trip the '.CP's, action will be taken as necessary.. Note that changes which nay be made in analytical methods as La result of_ Item II.K.3.30 would have to be factored into RCP trip cri-teria. Because implementation of Item II.K.3.30 is presently July 1, .1983, resolution of the RCP trip criteria may have to be delayed. 1 [
-ven ~u q Mr. Darrell G. Eisenhut ' June 18,1980 4 II.K.3.17. - Report on Outage of ECCS Components This item will require a substantial amount of manpower in order to re-search operations logs, correspondence, etc. for the necessary data. However, we feel that we will be able to meet the January 1, 1981, date for completion of our research. Report submittal will be made by . March 1, 1981. II.K.3.30.=- Revised Small-Break LOCA M:thods to Show Compliance With 10 CFR 50, Appendix K k The May 7, 1980, NRC letter from D. Eisenhut stated that clarifying infor-mation regarding implementation of this item would be provided in the May, 1980 version of NUREG-0660. Because the information was not included in the NUREG, a commitment to this item will be made after the implementation requirements are' received. II.K.3.31. - Plant Specific Calculations to Show Compliance With 10 CFR 50.46 Completion of this item is contingent upon completion of ' Item II.K.3.30. The time necessary.to complete plant specific calculations is dependent upon the degree of the changes which may be required in SBLOCf. analysis methods. III.D.3.4. - Control-Room Habitability Based on reviews performed 'in our FSAR and Safety Evaluation Report for ANO-2, our ANO-1 letter to Mr. R. W. Reid of your staff, dated January 10, 1980, and in accordance with reviews performed for IE Circular No. 80-03, we-believe the current ANO-1-and ANO-1 Control Room designs meet the re-quirements of this item. "In accordance with the errata sheets contained in a June 9, 1980, letter from O. G. Eisenhut, no response was made for Items II.K.3.25, II.K.3.29, and II.K.3.44. Because AP&L did not receive the errata sheets until June 16, 1980, this response.is being submitted late. 4,'e apologize for any. inconvenience-this may.have caused you. Very truly yours, g David C. Trim le Manager, Licensing DCT: MAS: s km _ _ - - - _ - _ _ _ - _ _ _ _ - _ _ _ -}}