ML19256F180
| ML19256F180 | |
| Person / Time | |
|---|---|
| Issue date: | 10/31/1979 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19256F178 | List: |
| References | |
| RTR-NUREG-75-087, RTR-NUREG-75-87 PSRP-9.2.2-R1, NUDOCS 7911210580 | |
| Download: ML19256F180 (2) | |
Text
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O U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Value-Impact Analysis Proposed Revision 1 Draft 1 STANDARD REVIEW PLAN SECTION 9.2.2 1.
PROPOSED ACTION 1.1 Description of and Need for the Proposed Action The preposed action will provide revised guidance to applicants concerning methods of review and acceptance criteria used by the NRC staf f in evaluating auxiliary cooling water systems (CWS) for nuclear power plants.
Specific changes to Standard Review Plan (SRP) Section 9.2.2 will:
Add cooting requirements for r. actor coolant pump seals and bearings, and a.
b.
Incorporate miscellaneous editorial changes.
1.2 Value/ Impact of the Proposed Action 1.2.1 NRC The proposed action will provide written guidance to be used by the staff in the review of applications and should therefore result in a more efficient review process. Since the revised guidance is currently being followed by the staff, there would be no impact.
1.2.2 Other Government Agenci s e
Not applicable, unless the government agency is an applicant, such as TVA.
1.2.3 Industry The proposed action will provide additional guidance to industry concerning the methods and criteria used by the staff during license applicatian reviews. Since the guidance is currently being issued by the staff in the form of standard questions, there should be no impact.
- 1. 2. 4 Workers (relative to ALARA)
Not applicable.
1.2.5 Public No impact on the public can be foressen.
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- 1. 3 Decision on Proposed Action A revision to SRP Section 9.2.2 incorporating the changes noted in Section 1 above should be issued.
9.2.2 '
7911210
e 2.
TECHNICAL APPROACH The proposed action cod;.*ies existing practice, and therefore a discussion of alternative technical approaches for the proposed action has not been included.
3.
PLAN FOR IMPLEMENTATION The proposed action represents a small improvement in safety or protection of the environment and warrants implementatio.i on new plants only.
It is important to note that a good initial design will provide an auxiliary CWS that complies with the requirements of the revised SRP.
There should be minimal impact on plants under con-struction permit review since an ASB Standard Question inquires about the reactor coolant pump CWS design. The acceptance criteria has been the same as that provided in the revised SRP section.
The revised guidance contained in SRP Section 9.2.2 should be implemented for new plants only.
4.
PROCEDURAL APPROACH The proposed action codifies existing practice in conjunction with system design review as outlined in the Standard Review Plan. Therefore, a revision to the SRP is the appropriate procedural approach.
5.
STATUTORY CONSIDERATION 5.1 NRC Authority The proposed action would be derived from the authority and safety requirements of the Atomic Energy Act through the Commission's regulations. In particular, Criterion 44 of Appendix A to 10 CFR Part 50 contains requirements for the design of cooling water systems for nuclear power plants.
5.2 Need for NEPA Assessment The proposed action is not a major action as defined by paragraph 51.5(a)(10) of 10 CFR and does not require an environmental impact statement.
6.
SUMMARY
AND CONCLUSIONS The proposed revision to 3RP Section 9.2.2 should be issued.
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UNITED ST ATES NUCLEAR REGULATORY COMMISSION f
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