ML19320D010
| ML19320D010 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/01/1980 |
| From: | Trimble D ARKANSAS POWER & LIGHT CO. |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| 1-070-01, 1-70-1, NUDOCS 8007180429 | |
| Download: ML19320D010 (3) | |
Text
,
ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 UTTLE ROCK. ARKANSAS 72203 (501)371-4000 July 1, 1980 1-070-01 Director of Nuclear Reactor Regulation ATTN:
Mr. Robert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Arkansas Nuclear One-Unit 1 Interim Reliability Evaluation Program (File: 0800.1)
Gentlemen:
The Arkansas Power & Light Company would like to participate in the NRC's research program for the Interim Reliability Evaluation Program (IREP) as discussed in the June 12 IREP meeting in Bethesda.
In par-ticular, we agree to include Arkansas Nuclear One, Unit 1, in the IREP research program. We feel that the IREP program is beneficial to both the NRC and the utilities, and are interested in developing a viable methodology for future IREPs.
We are concerned, however, about the vagueness in which the scope of the IREP research program was defined. For example, exactly what does the NRC expect to obtain from this research program concerning the method-ology? Was the methodology used in the Crystal River IREP not accept-able? If so, by which criteria was the methodology judged? We feel that another meeting between the NRC and the utilities involved in the research program is necessary to discuss these details prior to begin-ning the IREPs.
Each utility at the June 12 meeting was given a list of information required by NRC for the IREP effort. We have been in contact with our ANO-1 project manager concerning this request. The status is discussed in Attachment I.
We have cade some assumptions in our decision to participate in the IREP research program. These include:
1.
The full-time IREP team member from AP&L will function as both O7 analyst and liaison.
Information for the team will be re.
quested and transmitted through this person, with information 5
//
scog g
_e-cce scm,- mr,mree s erm
copies to the NRC project manager. Further AP&L may have more than one participant on the study team as necessary. We plan to have a person knowledgeable in plant operations as the full-time member and people knowledgeable in probabilistic assessment participate part-time as required. Our intent is to insure that both the site specific questions and the gen-eral methodology are appropriately addressed. The need for multiple participants arises since we have no one skilled in both plant operations and probabilistic assessment.
2.
AP&L will incur no costs other than the salaries and travel expenses of AP&L employees assigned to this project and the cost of providing the requested information discussed above.
In particular, AP&L will not be charged for any consultant costs associated with the IREP team, including site specific analyses requested by the team from AE firms, NSSS suppliers, or vendors. Also AP&L will not be charged for prorated office expenses for our full-time IREP team member. Of course, AP&L will assume the costs for any consultants recruited by AP&L outside the IREP team.
3.
The ANO-1 IREP team will be located in Albuquerque, New Mexi-Co.
4.
Issues raised during the IREP study will not become licensing issues until after the IREP report has undergone peer review and approval by AP&L. Our intent here is not to circumvent licensing issues, only those based on incorrect information.
The peer review and approval process should eliminate any incorrect issues.
If any of these assumptions are not correct, please inform us as soon as possible so that we may evaluate its impact on our decision to partici-pate.
The technical point-of-contact for IREP at AP&L is Mr. William T. Craddock, Manager Availability Engineering (phone 501-371-4132). All official re-quests should continue to be addressed through the normal channels.
Very truly yours, David C. Trimble Manager, Licensing DCT:WTC:nzk Attachment cc:
Mr. R. M. Bernero U. S. Nuclear Regulatory Commission 5650 Nicholson Lane, NL 5650 Rockville, Maryland 20555 i
l 1
F1
ATTACHMENT I Your.ay 23, 1980 letter requested information for the IREP study for ANO-1.
Through conversations with Mr. Guy Vissing of your staf f, the following commitments have been made:
1.
Up-to-date FSAR:
NRC will supply the necessary copies.
2.
Current Technical Specifications:
NRC will supply the necessary copies.
3.
A complete set of P&ID's:
AP&L will supply a current set of P&ID's by July 31, 1980.
4.
A set of emergency and operating procedures:
AP&L will supply this to you by July 31, 1980.
5.
LER's:
NRC will supply the necessary copies.
6.
Proposed modifications to the plant:
The available information will t.e supplied by July 31, 1980.
7.
System descriptions:
The FSAR contains the only available system descriptions.
8.
Manuals used in operator training:
The items used in o, aerator training include the FSAR, P&ID's, Tech. Specs., and procedures. These will be supplied as stated above.
9.
Minimum ECC and containment ESF systems which can realistical-ly prevent core melting:
This information has been supplied in the FSAR and in analyses which have been done in response to concerns raised since the TMI-2 incident. We will attempt to tabulate those reports which have been submitted to NRC and the date of submittal by July 31, 1980.