ML19351G176
| ML19351G176 | |
| Person / Time | |
|---|---|
| Site: | 05000480 |
| Issue date: | 12/02/1980 |
| From: | Jacobi W WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | Ahearne J NRC COMMISSION (OCM) |
| Shared Package | |
| ML19351G168 | List: |
| References | |
| NTD-80-126, NUDOCS 8102230224 | |
| Download: ML19351G176 (2) | |
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Nucmar center Westinghouse Water Reactor ser 233 BectricCorporation Divisions Pittsburgtt Pennsylvarua15230 w u Jacoot General Manager Nut'.ar Tochttology Olvision December 2, 1980
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NTD-80-126 The Honorable John F. Ahearne Chairman U.S. Nuclear Regulatory Comission 1717 H Street, N.W.
Washington, D.C. 2L555
Dear Chairman Ahearne:
f Westinghouse Electric Corporation has long been an advocate of standardi-zation in nuclear power plant design having first applied the standardi-zation concept in our designs in 1970. Our RESAR-0 and RESAR-3 standard licensing documents were produced and submitted even prior to the the Following AEC's c.7.etacement of their standardization policy in 1973.
announcement of the policy, Westinghouse submitted and obtained oreliminary design approvals for three reference NSSS designs:
RESAR-41, PDA #3, dated 12/31/75 (3800 MWt)
RESAR-35, PDA #7, dated 12/30/76 (3425 MWt)
RESAR-414, PDA #13, dated 11/14/78 (3800 MWt)
Wes..nghouse has applied for and was granted two-year extensions to both its RESAR-41 and RESAR-3S preliminary design approvals.
Prior to the accident at Three Mile Island, Westinghouse Electric Corporation was actively working with AIF and the NRC's Standardization Branch in advancing the standardization concepts for use in operating license reviews.
However, since Three Mile Island, the Staff has been relatively silent on the subject of standardization while attention has been appropriately focused on those plants in operation end under construction.
There is still a continued industry interest in standardization as evidenced by the Office of Technology Assessment Worksbr m Nuclear Power Plant Standardi7. fon held in September of this yea, by activities of AIF's Comittee on Reactor Licensing and Safety. Hov er, for standardization to remain effective as a viable option for the future, the NRC should take A immediate and positive action to endorse its comitment to the program.
first step should be a further extension to existing preliminary design
.ipproval s. One of our PDAs, RESAR-41, will expire in December of this year while RESAR-3S and RESAR-414 will expire in December 1981 and November 1983,
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The Honorable John F. Ahearne Decem'ar 2, 1980 4
I respectively. The NSSS designs documented in those RESARs have not been l invalidated by the accident at Three Mile Island, and they remain the basis for current Westinghouse designs being offered in the marketplace. Other vendors and architect engineers are faced with similar PDA expiration dates.
Westinghouse recommends that the NRC keep the PDAs active as a reference base. Modifications of the PDA document to address current issues, such as TMI-related requirements, can be made, as necessary, via amendments at the time a utility wishes to use the reference system. Such an approach precludes costly resubmittal of the entire reference document because of an administratively set expiration date and would reduce review time. The amencment approach will be the most cost-effective way to maintain the standardization program while conserving valuable resources and will assist in keeping tne nuclear option available and competitive in the current energy situation and business environment.
I request you give serious consideration to this recommendation. Members of my staff are available to work with your staff in expanding upon this approach.
i' Sincerely,
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W.m.
cc: H. Denton, NRR P. Eisenhut, NRR f
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