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A. SchwIncsr
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P.O. Box 1260, Lynchburg, Va. 24505 Telephone: (804) 384-5111 September 15, 1975 Mr. Benard C. Rusche, Director
. Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Coinnission Washington, D.C.
20555
Dear Mr. Rusche:
This is to inform you that Babcock & Wilcox plans to submit a standard safety analysis report (B-SAR-205) for NRC Staff review under the reference system concept described in Appendix 0 to 10 CFR 50.
The B-SAR-205 describes B&W's standardized 205 fuel assembly nuclear steam system, which is essentially identical to the design described in five previously submitted construction permit applications. The scheduled filing date is October 31, 1975.
The discussions in our September 3, 1975, meeting were a positive influence on our decision to submit the B-SAR-205 as a reference SAR for your review.
I would like to take this opportunity to emphasize some of the key points from that meeting and to offer our support to the NRC's effort to develop a viable standardized licensing process.
In order for standardized licensing to be a success, it must be possible to design, license and construct a number of plants of identical design. To do this, a standard design approval must be valid long enough to encompass at least 10 to 15 nuclear units. While the design approval is effective, it will be necessary to limit the introduction of new regulatory requirements to only those needed for compelling safety reasons. We strongly urge that the time span of a preliminary design approval be longer than the two years now discussed in WASH-1341. We believe a three-to-five-year life is desirable, and we are encouraged by your remarks that the NRC is evaluating a two-to-five-year life.
We agree that the standard review plans now being prepared at NRC can be an important means of controlling the introduction of new regulatory requirements.
We support the NRC's policy to conduct reviews'in accordance with these plans, and to provide that changes to the plans or deviations from them be considered by the Regulatory Requirements Review Committee and approved by the Director of Regulation. When considering a change or deviation from the review plans, we believe it is appropriate to balance the resources required to implement new regulatory requirements against the positive gains in public safety.
B&W understands that the identification of safety-related interface criteria in standard safety analysis reports has proven to be a more difficult task than expected. We are in general agreement with the industry proposal to form a joint NRC-industry task group to prepare a standard format and content guide for safety-related interface criteria on a high priority basis, and we desire to participate in such a task group.
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{ Babcock &Wilcox Mr. Benard C. Rusche September 15, 1975 j
As we discussed on September 3, the B-SAR-205 is based on a licensed core power level of 3800 MWt, in conformance with Regulatory Guide 1.49.
The B-SAR-205 l
, also includes provisions for a utility applicant to submit a construction permit application for a licensed core power level of 3600 MWt by referencing r
The nuclear steam system hardware will be the same at either power B-SAR-205.Since this approach appears acceptable to the NRC, the B-SAR-205 will-level.
be submitted as a single application, notwithstanding the power level flexi-l bility that we have provided.
Since the B-SAR-205 design is essentially identical to the one reviewed by the l
NRC Staff in several previous construction permit applications, we were pleased ble.
B&W will work to confirm that an accelerated review schedule will be possp with your Staff to support and improve upon an 11-month review schedule.
In this connection, we support the policy of assiCning NRC personnel to the B-SAR-205 review who were involved in the review of previous PSAR's utilizing the B&W 205 fuel assembly nuclear steam. system. We believe that this is an l
l important step towards ensuring a timely, yet thorough review. _ To assist you in doing this, we arc making this early indication of our intent to file the B-SAR-205 for your review.
The submittal of B-SAR-205 for reference system review reflects B&W's constitment to standardization and our support for the NRC's standardization policy. IJe anticipate that the B-SAR-205 will aid the NRC in achieving its standardization goals, and will provide improved utilization of resources for B&W and our utility customers.
Sincerely yours, b
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64<) M0F05ED AGENDA - BACECRDCND OR UD6
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INTRODUCrim Purpose of meeting is to obtain information to aid in making a decision ca ethnittal of B-SAR-205 as a reference 5511 md on M=4ng of sthuittal if the decision to submit is made.
e II. DISCUSSIN OF ISSUES A.
Current Policy - General The basis for present ptenning is the AEC policy stated in h'15-1341 for Beferwnce and Duplicate plants and the policy document dated July 1974 for Saplicate Plants. Recent industry experiencer particularly with tha replication option, indicates some inconsistency between staff prantice and the stated policy. Assurance that the former AEC policies and stated practices on standardization are being implemented by NRC is vital to being able to sale any decision regarding standard plant licensing via any of the options.
B.
Need for NEC Policy Statement in January 1977 Begulatory Guide 1.49, " Power levels of Nuclear Power Plants," states the NEC will issue notice of its intent to consider applications at core thermal power levels greater than 3800 megawatts at least two years prior to acceptance of such applications and also states that such acceptance will be after 1/1/79.
Can the nuclear industry expect a policy statement by the NRC in January 1977 regarding the seceptabi.11ty of higher power level plants? A policy statement at that time, which includes a schedule fer further consideration of increasing the power laval restriction (if the decision la negetive at that time), will be a substantial standardi-zation pinnning tool for the nuclear plant suppliers and ceners.
C.
Effect of Licensing Reform Iagislation,
The AEC standardization policy statement of March 5,1973 stated that standardized designs would receive priority in scheduling and staff q _
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manpower assignment. The recent proposed licensing zuform legislation in Section III gives NEC the power to, discriminate between utility e
applications. la addition. there has been a noted lack of participation by A-g firms in reference SSAR licensing. It is tsiderstandabla that the Us are NEC would adopt policies that would encourage scandardization.
concerned, however, that there is a possibility of it becoming extremely difficult for a custou plant application to be approved an a timely schedule in the future in the interest of promoting standardization.
D.
Mine-Month Beview for 5-SAR-205 Tha B-SAR-205 design is essentially identical with c2ie 205 fuel assembly design previously reviewed through the' SEE _ stage on three CP applications and with one other application now under review. Since substantial NRC review for this plant has already been perforned, BW anticipates a much shortar review schedule, for the PDA. than is indicated in WASE-1341, or has 6een experienced by other vendors, or was proposed for our B-SAR-241.
B&W believes 9 months to be an adequate and sufficient review period for
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the PDA and vill support this schedule }.f the 5-SAR-205 is filed.
Can
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the NRC Staff provide a constitment to this schedule or propose some other d
schedule at this time in keeping with the policy of assiping priority?
L Fees for the B-SAR-205 Review We understand the present intent is not to charge review fees for a reference SSAR until it is adopted by a CF application. Can this be verified? We need to know what tha schedule is for a final rule on fees i,
and the applicability of this rule on SSAR's in process of review.
F.
Frequency of Updating a Reviewed and Approved Standard NSS We are concerned that the prEsent rate of change in licensing requirements in fact negates the chances for standardization.
For standardization to be successful, industry must design and NRC sust license a nunber of identical plants. The updating process after preliminary design approval ha.s the potential for negating the benefits of standardization. We under-l stand NRC is now developing the detailed' criteria for updating reference
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standard SAR's. No urgs that these critaria be formulated so as to obtain full benefit from standardization. Our specific suggestions ars leinf =f se the ' number of "different" p1* ate by extending the laterval between updates beyond the present two years mentioned in WASE-1341. 7his is especially needed in cases where a
=f=1=== number of planta have not matarin14=d to maka use of the $5AL Limit the changes to be unde at an update to those that can be l
justified on a cost-benefit basis.
Provide for consistency in licensing requirements between tha differsat SSAR's. %5.s any require a consistent implementation data for updates to avoid providing an unfair at. vantage in the market to the vendor who updates last.
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I G.
Power Level l
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B&W's present intent is to offer the 255 fuel assembly plant with identical hardware, but at two power levels - 3600 and 3800 W.
ne difference between the plants will be operating condit. ions only, not hardware. De l
Babcock-205 has higher thermal efficiency at the 3600 W rating than at 3800 W and thus may be more desirable to some utilities. We would like to cover both poter levels by a single review,.so B-SAR-20S will contain analysis for 3800 Wt.
At the final design stage, some applicants may j
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prefer operation at 3600 W rather than the 3800 W 1evel. In these cases j
either a custom ISAR or an addition to B-SAR-205 will provida separate analysis and operating limitations for the 3600 W power level. We would i
l like a constitment that B-SAR-205 may be used in this manner.
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7-
..