ML20140B473
| ML20140B473 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Callaway  |
| Issue date: | 09/04/1981 |
| From: | Petrick N STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| SLNRC-81-86, NUDOCS 8109140200 | |
| Download: ML20140B473 (3) | |
Text
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SNUPPS Standardized Nuclear Unit Power Plant System 5 Choke Cherry Road Nicholas A. Petrick R vH land 20850 Executive Director September 4,1981 SLNRC 81-86 FILE: 0541 P
SUBJ: ETSB Review s[
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f7 AllL h Mr. Harold R. Denton, Director pJ SEp J J 79g7, ug-Office of Nuclear Reactor Regulation y,,,,,,,
U.S. Nuclear Regulatory Commission q
commae Washington, D.C. 20555 b
4.s Docket Nos.: STN 50-482, STN 50-483, and STN 50-486
Dear Mr. Denton:
The referenced letter provided FSAR changes that were needed by the Effluent Treatment Systems Branch in order to complete their review of the SNUPPS FSAR.
I: discussions with Dr. Gordon Edison, NRC project manager for the SNUPPS applications, it was learned that additional information is required. The enclosiare to this letter is a change to the information provided in the reference. The enclosure and the other changes provided in the reference will be incorporated in the next revision of the SNUPPS FSAR.
Very truly yours, Nicholas A. Petrick RLS/dck/3a24 cc:
J. K. Bryan, UE G. L. Koester, KGE D. T. McPhee, KCPL W. A. Hansen, NRC/ Cal T. E. Vandel, NRC/WC w(
8109140200 810904 PDR ADOCK 05000482 A
pop J
SNUPPS i
In view of the fact that these systems are designed to preclude I
operation during an accident, upgrading the testing and sur-y l
veillance of these systems is not justified.
- ( IN SFR.T D
?
4 18.3.4.3 Conclusion The SNUPPS design includes provisions to insure the integrity of fluids systems which are postulated to contain highly contaminated fluids following a design basis accident.
The I
provision will be based on the preservice and inservice tests required by the ASME Code.
These provisions provide assurance that thes'e systems will perform their intended functions, including leaktightness, following a design basis accident.
This commitment satisfies Item III.D.1.1 of NUREG-0737.
18.3.5 IMPROVED IN-PLANT IODINE INSTRUMENTATION UNDER ACCIDENT l
CONDITIONS (II.D.3.3)
Refer to each Site Addendum.
18.3.6 CONTROL ROOM HABITABILITY (III.D.3.4) 18.3.6.1 NRC Guidance per NUREG-0737 Position p
In accordance with Task Action Plan Item III.D.3.4 and control room habitability, licensees shall ensure that control room operators will be adequately protected against the effects of accidental release of toxic and radioactive gases and that the nuclear power plant can be safely operated or shut down under design basis accident conditions (Criterion 19, " Control Room,"
of Appendix A,
" General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50).
Clarification (1)
All licensees must make a submittal to the NRC regardless of whether or not they met the criteria of the referenced Standard Review Plans (SRP) sections.
The new clarifica-tion specifies that licensees that meet the criteria of the SRPs should provide the basis for their conclusior that SRP 6.4 requirements are met.
Licensees may estab-lish this basis by referencing past submittals to the NRC
' and/or providing new or additional information to sup-plement past submittals.
(2)
All licensees with control rooms that meet the criteria of the following sections of the Standard Review Plan:
2.2.1-2.2.2 Identification of Potential Hazards in Site g
- Vicinity, 2.2.3 Evaluation of Potential Accidents, and i
~'
6.4 Habitability Systems Rev. 5 18.3-4 7/81 J
INSERT D The.SNUPPS Utilities will have a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids in a post-accident situation. The programs will meet Item III.D.l.1 of NUREG-0737 and will include the following:
1.
The implementation of all practical leak reduction measures for all systems that could carry radioactive fluid outside of containment.
2.
The measurement of actual leakrates with the systems in opera-tion and the reporting of the results to the NRC.
3.
A continuing leak reduction pro' gram of preventive maintenance to reduce leakage to as-low-as-practical levels. This program will include periodic integrated leak tests at intervals not to exceed each refueling cycle.
Detailed information on the program and a list of any excluded systems and their justification for exclusion will be provided at least four months prior to fuel load of each SNUPPS unit.
RLS/dck/3a25