ML20076K087

From kanterella
Revision as of 10:39, 26 April 2020 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Clarifies 830415 Response to Suppl 1 of NUREG-0737.Program Plan for Control Room Design Review Will Be Submitted by 831015.Reg Guide 1.97 Review Will Be Completed by 841101. Schedule for Safety Parameter Display Sys Reasonable
ML20076K087
Person / Time
Site: Pilgrim
Issue date: 07/01/1983
From: Harrington W
BOSTON EDISON CO.
To: Vassallo D
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737 83-768, NUDOCS 8307080045
Download: ML20076K087 (2)


Text

.

<* e*

BOSTON EDISON COMPANY 800 BOYLBTON STREET BOSTON. MAsBACHusETTs 02199 WILLIAM D. HARRINGTON esman wees ensaioswv July 1, 1983 BECo Letter No.83-168

' Mr. Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 License No. DPR-35 Docket No. 50-293

Subject:

Clarification of BECo Response to Supplement 1 to NUREG 0737

References:

(A) BECo Letter to NRC dated April 15, 1983.

(B) Telecon J.M. Ful ton, T.M. Thurston (BECo) with K. Eccleston (NRC) June 15, 1983.

Dear Sir:

Reference (A) provided you with our initial response to the subject item. Based l on conversations with your staff, Boston Edison is providing the requested further clarification of our response.

l Control Room Design Review (CRDR) 1 We intend to submit our program plan for CRDR by October 15, 1983.

Regulatory Guide 1.97 We have revised our schedule and now intend to complete our Reg. Guide 1.97 review by November 1, 1984.

Safety Parameter Display System (SPDS) l We have reviewed our proposed schedule. Unfortunately, we will not be able to l revise our current schedule. The basis for this conclusion is our review of the l manpower requirements and the impact of future workload. Our review indicates the engineering resources utilized for these tasks are typically the same groups (Instrumentation and Control Engineers and System Safety Engineers) who are

involved with other NRC mandates. These resources are being utilized on such t issues as Environmental Qualification 10CFR50.49, Reactor Water Level Improve-l ments, Inadequate Core Cooling, Regulatory Guide 1.97, and Control Room Design l Review. We believe the existing schedule adequately distributes our resources and is responsive to NRC concerns. Furthermore, in consideration of our 8307080045 830701 PDR ADOCK 05000293 d P PDR $0J f

BOSTON EDISON COMPANY Mr. Domenic B. Vassallo, Chief Page 2 upcoming Refueling Outage and the associated potential workloads, we consider the original schedule reasonable and achievable and intend to work toward that end.

We trust this is responsive to your needs. However, should you have any ques-tions, please contact us.

Very truly yours, TMT/ mat b

i t

- - - ,-- ..m.,,,e,,, __,.__ .- - _ _ . - ._y,,,,. , _ _, y.,, _ -. . - _ - . . . - . ~ - . _ . _ , _ _ _ _

. _ . . _ _ . .