ML20214G944
| ML20214G944 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 05/03/1978 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| CON-WNP-0225, CON-WNP-225 NUDOCS 8605230075 | |
| Download: ML20214G944 (2) | |
Text
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DA Docket Ho.: 50-397 MEMORANDUM FOR:
S. A. Varga. Chief, Light Water Reactors Branch rio. 4, DPM FROM:
R. L. Tedesco, Assistant Director for Plant Systems, DSS
SUBJECT:
ACCEPTANCE REVIEW FOR WPPSS-2 Plant Name: Washington Public Power Supply System Nuclear Project #2 Licensing Stage: 0L Docket tiumber: 50-397 Responsible Branch: LUR No. 4 Project flanager:
D. Lynch Requested Completion Date: April 19,1978 Review Status: Acceptance Review Complete The Containment Systems Branch has performed an acceptance review of Section 6.2 of the Washington Public Power Supply System t!uclear Project flumber 2 Final Safety Analysis Report. 3ased on.'onc review we conclude that Section 6.2 is not acceptable for the initiation of a detailed technical review, primarily because of the status of the plant design assessment report and the applicant's plans to utilize a catalytic recombiner. With **espect to both of these areas, the applicant has not provided enough information to allow for initiation of our review.
In addition, there are several areas per 1.70 where the information is incomplete. These areas include reactor cavity and reactor support analysis, isolation, and containment leak testing.
ife have also recently received the plant design ' assessment report for WPPSS.
This report addresses the associated loads for the SRV and LOCA pool dynamic phenomena. The applicant has referenced Revision 3 to the DFFR a's his justi-fication basis for a significant number of the loads. This revision is not scheduled to be subtaitted to the staff before the Sumer of 1978.
- Further, it appears that the applicant may have dettated slightly from the analytical methods proposed in this DFFR. However, there is insufficient information to make a final detemination in this area. We have, therefore, requested additional infomation to clarify the applicant's analytical models and program. In light of the status of Revision 3 to the DFFR and also the possible exceptions to the analytical procedures, we believe that a meaningful
!1PPSS review schedule in this area cannot be made without further definition.
CONTACT:
JZwolinski, CSS X27711 l
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S. A. Varga MAY 3 19to In addition to our review status relative to LOCA and SRV pool dynamic loads, the applicant has proposed the use of a catalytic reconbiner. The FSAR does not provide any information concerning the design and test qualification of this type. Therefore, it is anticipated that this will require a substantial review effort.
It should be noted that in the CP SER, this item was indicated to be resolved as a post-CP item. This was never done. We have enclosed a series of detailed questions highlighting the type of steam and test informa-tion which are felt to be necessary to properly evaluate this recombiner design.
However, it should be noted that at this time, the FSAR does not contain any information other than a mention of the type of recombiner to be used.
We have also identified several deficiencies in the FSAR. These are listed in the enclosure. Areas of review which will require additional infomation include isolation, c(atainment leak testing program, containment purge subcompartment analysis, teean bypass, and bypass leakage of the secondary containment. Regarding bypass leakage, we have attached the letter which was sent to Zimar and Shoreham on this suoject. A similar letter should be sent to WPPSS reflecting our concern.
Oric!nal signed by Rabcet L. Tedesco Robert 1.. Tedesco, Assistant Director for Plant Sy:.tems Division of Syste:3s Safety
Enclosure:
DISTRIBUTION:
As stated DOCKET FILE 50-397 NRR READING cc:
S. Hanauer CSB READING R. Mattson FS READING R. Boyd R. Hartfield
- 9. Lynch R. Tedesco
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