ML19316B208

From kanterella
Jump to navigation Jump to search
Responds to Requesting Info Re New Safety Stds W/ Which Facility Must Comply Prior to OL Issuance.Facility Response to post-TMI Improved Safety Recommendations Reviewed.License to Load Fuel & Test Issued 800418
ML19316B208
Person / Time
Site: Salem PSEG icon.png
Issue date: 05/22/1980
From: Dircks W
NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To: Roth W
SENATE
Shared Package
ML19316B209 List:
References
NUDOCS 8006120074
Download: ML19316B208 (2)


Text

-

  1. JU /A we%

$8 UNITED STATES yhe p,

NUCLEAR REGULATORY COMMISSION.

g g

wAssinoTon. o. c. 2csss

%..v.../

MAY 0 3 MO The Honora.ble William V. Roth, Jr.

United States Senate i

Wash bgton, D. C.

20510

Dear Senator Roth:

In ycur letter of April 9,1980 to Mr. Carlton Kamerer, you requested that we i

provide you with "a detailed explanation of the new strict safety standards" that the Salem, Unit 2 nuclear power plant must comply with prior to licensing as a rssult of the Three Mile Island, Unit 2 (TMI-2) accident.

The proposed additional requirements that have bee' identified as a result of n

THI-2 for near-term operating license applications such as for Salem, Unit 2, were initially discussed in a January 5,1980 memorandum from the NRC Executive.

Director for Operations to the Comissioners, "TMI Action Plan Prerequisites for Resumption of Licensing". On February 6,1980, a revision of this list of recomendations, based on the latest draft of the TMI Action Plan as of that date, was prepared and discussed with the Comission. The proposed requirements were listed in two categories; those required prior to fuel load and low power testing operation up to five percent power and those required prior to operation above five percent pcwer.

The proposed requirements were ' developed from all available sources, such as the recomendations of the NRC Bulletins and Orders Task Force, the Pret.i@ntial Comission to Investigate TMI-2, and the NRC Special Inquiry Group, and those which resulted from the NRC Lessons Learned Task.Ferce Short Term Recomenda-tions (NUREG-0578), and the Lessons Learned Task Force Final Report (NUREG-0585).

Those proposed requirements in the February 6,1980 list which resulted from the Lessons Learned Task Force Short Term Recomendations (NUREG-0578), and those resulting from the Advisory Comittee on Reactor Safeguards review of that document and the additional requirements of the Director, Office of Nuclear Reactor Regulation, were previously approved by the Comission. On September 27, 1979, a letter was issued transmitting these proposed requirements to t11 pending operating license appMcants. On November 9,1979, a letter clarifying these propost.d requireme ^. was issued to all perding operating license applicants to assist in their understanding of the requirements.

The response of the Public Service Electric anet Gas. Company to our letters for the. Salem, Unit 2 plant had been the subject'of NRC staff review since-October 1979.

Meetings were held with the applicants in Bethesda on November 20 and December 11, 1979, and February 26, 1980.

Site visits were made on January 10 and 11, and February 27, 1980 to check hardware installation, review proposed su;: port centers, and to review specific administrative procedures relating to a

cperating personnel and accident response.-

~

1

'l 8 0.0612 00N d

The Menorable William V. Roth, Jr. In addition, for all the remaining items in the February 6,1980 list, the NRC staff and the applicants have had ongoing reviews and meetings concerning these requirements and the applicants' responses to these additional items. Further site visits were held, for example, a March 5-7, 1980 visit by a team headed by an Office of Inspection and Enforcement leader and composed of the NRR licensing project manager, the Office of Inspection and Enforcement site representative, and technical members from NRR.

They evaluated the onsite and offsite support centers and their staffing and the installed communications system between the plant and NRC Incident Response Center.

This evaluation included the review of licensee management organization and managerial capabilities.

Each applicable propored fuel load requirement and low power testing requirement in the Februar; 6,1980 listing is discussed in de. tail ia Part II of Supplement No. 4 to the Salem Safety Evaluation Report. For your information, we are pro-viding you with a copy of this document. The discussion of these requirements includes sections titled Position and Clarification which are repeated from the' generic letters to operating license applicants as discussed above.

The NRR staff's evaluation cf Salem, Unit 2, as provided in Supplement No. 4, was discussed with the Commission on April 16, 1980. As a result, the Commission. authorized the staff to issue a license to Salem, Unit 2 for fuel leading and low power testing up to five percent power. Such a license was issued on April.18,1980. The April 18, 1980 license imposes the various pro-posed requirements as conditions on the Salem 2 license.

I would like to point out that prior to authorizing a full pcwer license for Salem, Unit 2, the additional TMI-2 related proposed requirements for operation above five percent power also need to be addressed. These additional require-ments will be discussed in a subsequent supplement to the Safety Evaluation Report.

I am pleased to have had this opportunity to respond to your request.

If you have any other questions regarding this matter, please let me know.

Sincerely, JSigned) I. Kevin Cornell

\\

i

[#' William J. Dircks, Acting Director for Operations

Enclosure:

As stated

... ~.

y