ML17290A705
| ML17290A705 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 10/20/1993 |
| From: | Rosalyn Jones Office of Nuclear Reactor Regulation |
| To: | Quay T Office of Nuclear Reactor Regulation |
| References | |
| TAC-M87075, NUDOCS 9310270100 | |
| Download: ML17290A705 (3) | |
Text
October 20, 1993 MEMORANDUM FOR:
T.
R., quay, Project Director (13-E17)
Project Directorate V
Division of Reactor Projects IV,V FROM:
SUBJECT:
Robert C. Jones, Chief Reactor Systems Branch Division of Systems Safety 5 Analysis WASHINGTON PUBLIC POWER SUPPLY SYSTEM NUCLEAR PROJECT NO.
2 POWER UPRATE REVIEW (TAC NO. M87075)
Enclosed is a Reactor Systems Branch Request for Additional Information based on our review of the subject information provided by the licensee for the WNP-2 power uprate, and change in safety/relief setpoint tolerance license amendment.
In order to meet the tight schedule proposed for this review by your project directorate, a timely response is needed.
/s/
Enclosure:
As stated cc:
J. Clifford Robert C. Jones, Chief Reactor Systems Branch Division of Systems Safety
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WNP-2 RE VEST FOR INFORMATION 1.
Should RPS and RRC be defined in the glossary of terms?
2.
In Section 2.4 of NEDC-32141P, the stability discussion did not contain a
commitment to follow the guidance contained in NRC Bulletin 88-07 and the Supplement 1.
Do you plan to follow this guidance?
3.
In Section 3.4 of NEDC-32141P, the licensee did not commit to perform power uprate tests on the RRC system to demonstrate flow control over the entire recirculation flow range that WNP-2 plans to operate, as discussed in the GE generic report NEDO-31897 (power uprate generic guidance report).
These tests provide assurance that no undue vibration or other phenomena occur at power uprate and/or Extended Load Line Limit (ELLL) operation.
Is the licensee planning to perform these tests prior to operating in these regimes?
4.
In Section 9.3.2 of NEDC-32141P, the Station Blackout (SBO) event is discussed.
Will this event be evaluated with power uprate and including ELLL operating conditions to assure that systems needed to respond after power has been restored are designed to operate for the peak suppression pool temperature expected for this event?
5.
In Section 9.3. 1 of NEDC-32141P, provide an explanation as to why the Loss Of Feedwater (LOFW) event is more limiting for WNP-2 than the Loss Of Offsite Power (LOOP) in the generic Anticipated Transients Without Scram (ATWS) analysis.
Provide assurance that the generic evaluation referenced by WNP-2 is valid for SNP fuel.
Provide the results of the analysis or reference where they are contained if they are elsewhere in your submittal.
6.
The transient analysis results for uprate are presented in Table 9-2 of NEDC-32141P.
Please define MCPR, for the hMCPR column for the Slow Recirculation Increase transient.
7.
In your SAFER/GESTR-LOCA analysis report (NEDC-32115P) you provide a
discussion for Single Loop Operation (SLO) thermal limits.
The evaluation assumes there will be no MAPLHGR or PLHGR reduction for SLO.
The SLO nominal and Appendix K PCTs are higher than for two loop operation.
Provide assurance that the upper bound PCT is less than 1600'.
Are there any reductions on these thermal limits for operating in the ELLL regions such that the PCTs for SLO will be less than for two loop operation?
Will there be any increase in the SLMCPR for SLO because of incr eased uncertainties?
9.
In your GE-NE-187-24-0992, Rev.2 report discussing SRV setpoint tolerance and the number of SRVs out-of-service (OOS) evaluation, there appears to be no reference to a generic GE Nuclear Energy Licensing Topical Report (NEDC-31753P).
This report explains what plant specific analyses are needed to assure no safety limits are exceeded.
There also was an NRC Safety Evaluation Report prepared upon review of this generic report.
Why did you not reference these reports?
/