0CAN108507, Forwards Revised NUREG-0737,Suppl 1 Integrated Implementation Plan.Status & Tasks Performed in Last 6 Months Described,Including Control Room Design Review, Reg Guide 1.97,SPDS & Emergency Operating Procedures

Forwards Revised NUREG-0737,Suppl 1 Integrated Implementation Plan.Status & Tasks Performed in Last 6 Months Described,Including Control Room Design Review, Reg Guide 1.97,SPDS & Emergency Operating Procedures

ML20198B599
Person / Time
Site:	Arkansas Nuclear
Issue date:	10/30/1985
From:	Enos J ARKANSAS POWER & LIGHT CO.
To:	Thompson H Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097 0CAN108507, CAN108507, GL-82-33, NUDOCS 8511070086
Download: ML20198B599 (4)

Text

w ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 UTTLE ROCK. ARKANSAS 72203 (501) 3714000 October 30, 1985 0CAN108507 Mr. Hugh L. Thompson, Jr. Director, Division of Licensing Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555

SUBJECT:

Arkant's Nuclear One - Units 1 & 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6 NUREG-0737 Supplement 1 Update Gentlemen:

On April 15, 1983 in our ietter 0CAN048312, AP&L submitted to the NRC our response to NUREG-0737 Supplement 1 (Generic Letter 82-33). Subsequent to that letter, updates were provided regarding our progress on October 20, 1983 (0CAN108305), April 30, 1984 (0CAN948406), November 9, 1984 (0CAN118403) and May 7, 1985 (0CAN058504). This letter is provided to update you regarding our present status and to briefly describe the tasks performed over the previous six months. The attached figure is a revised version of the Integrated Implementation Plan (Figure 2-2), of our April 15, 1983 response. The shaded boxes indicate tasks which have been ccmpleted.

A brief summary of our progress in each of the topic areas is presented below.

Control Room Design Review AP&L submitted the Control Room Design Review (CRDR) program plan for Arkansas Nuclear One, Units 1 and 2, on November 25, 1983 in our letter BCAN118310. The actual review effort began in February, 1984. In response to a request by the NRC in a letter dated March 6, 1984 (0CNA038415), AP&L provided additional details regarding the schedule, scope and preliminary results of the CRDR program during a meeting with the NRC staff in Bethesda, Maryland on May 2,1984. A summary of this meeting was documented in Mr. Guy Vissing's letter to AP&L dated June 7, 1984 (0CNA068426).

Subsequent to that meeting, the NRC issued confirmatory orders on June 14, 1984 (0CNA068421) which confirmed the previously committed schedules to submit the ANO-1 Final Summary Report to the NRC by August 14, 1985 and the ANO-2 Final Summary Report by May 5, 1986. The ANO-1 Final Summary Report was submitted by our letter dated August 14, 1985 (ICAN088504).

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• Mr. Hugh L. Thompson, Jr. 2 October 30, 1985

! Subsequently, during the week of September 16, 1985, an NRC review team i performed an on-site audit of the CRDR program. As a result of this audit 4 and subsequent discussions with the NRC staff, AP&L provided additional i

details regarding sch2dules for CRDR corrective actions in our letter dated

October 18, 1985 (ICAN108510).

i j As stated in our last update, the ANO-2 CROR program is well underway with l further progress made in several areas. The validation and verification,

, identification and assessment of control room related HEDs are now complete.

These blocks are shaded as complete on the attached Figure 1. The ANO-2 effort is on schedule for submittal of the Final Summary Report to the NRC by May 5, 1986.

l 1 Regulatory Guide 1.97 i

! On June 25, 1984 AP&L submitted the ANO-1 Regulatory Guide 1.97 position i document in our letter ICAN068402. The ANO-2 position document was

! submitted on April 13, 1984 in our letter 2CAN948404. The planned

! modification schedules for each unit were provided in these submittals.

4 The NRC's response to the ANO-1 position document, dated March 20, 1985 (1CNA038595) was received in our offices en April 1, 1985. The NRC's l

response to the ANO-2 position document, contained in NRC letter dated April ,

30, 1985 (2CNA048506), was received on May 3, 1985. AP&L addressed the open J items in tnese responses in the requested 60 day time period by letters

dated May 28, 1985 (ICAN058507) and July 1, 1985 (2CAN078501) for ANO-1 and 3 2, respectively. Modifications planned for the 2R4 refueling outage were implemented during the outage, which took place during the first quarter of 1985. Future modifications for both units as planned for the IR7, 2R5 and 2R6 refueling outages are currently on schedule.

i

In the course of completing the necessary EQ documentation, it has come to j our attention that certain Reg. Guide 1.97 variables previously thought to t j be qualifiable should in fact be replaced. These variables are the two RHR

heat exchanger outlet temperature elements on ANO-1, and the volume coatrol i tank level, charging flow, letdown flow and RHR system flow transmitters on

ANO-2. As specified in the ANO-1 and 2 position documents, these two ANO-1

! temperature elements will be replaced during the IR7 refueling outage and l these four ANO-2 transmitters will be replaced during the 2R6 outage.

1 l Emergency Operating Procedures

A comparison between the ANO-1 E0P Technical Guideline and the NRC-approved l Babcock & Wilcox guideline as requested in the NRC's letter of July 26, 1984

, (ICNA078401) was submitted by our letter dated July 2,1985 (ICAN078503).

1 The ANO-2 E0P Technical Guideline was submitted to the NRC by our letter l 2CAN128403 dated December 5, 1984. The ANO-2 E0P was implemented during the

! 2R4 refueling outage which ended in Spring 1985.

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i

Mr. Hugh L. Thompson, Jr. 3 October 30, 1985 Safety Parameter Display System / Emergency Response Facility As mentioned in our last update, both the ANO-1 and 2 SPDS and the Primary and Secondary Technical SLpsort Centers have been declared fully operational. Further enhancements will continue to be made to the systems based on subsequent operational experience and input from plant operations.

General operator comments ccacerning the SPDS continue to be extremely favorable.

By letter dated August 7, 1985 (0CNA088507), the NRC requested additional information in order to complete their review of our SPOS Safety Analysis Report submittals. AP&L provided a response to this request by our letter dated October 28, 1985 (0CAN108504).

This concludes our update. Another update is scheduled for submittal in April, 1986.

Very truly yours,

'f',4 /,/

/

J. Ted'fhos f g[S/JS"" ~

Manag' p f, Licensing JTE:RBT

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