ML18092B246
| ML18092B246 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/08/1986 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| LCR-83-14, NLR-N86101, NUDOCS 8608140109 | |
| Download: ML18092B246 (3) | |
Text
Public Service Electric and Gas Company Corbin A. McNeill, Jr.
Vice President -
Public Service Electric and Gas Company P.O. Box236, Han cocks Bridge, NJ 08038 609 339-4800 Nuclear NLR-N86101 Ref:
LCR 83-14 Off ice of Nuclear Reactor Regulation United States Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 20814 Attention:
Mr. Steven A. Varga PWR Project Directorate #3 Division of PWR Licensing A
Dear Mr. Varga:
SUMMARY
OF TELECON TO DISCUSS LCR 83-14 ACCIDENT MONITORING INSTRUMENTATION SALEM GENERATING STATION.
UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 The subject telecon was held on Wednesday, July 30, 1986 between Mr. Jay Lee of the NRC staff and Messrs. J. Leech, J. Clancy and W. McTigue of the PSE&G Nuclear Department.
The topic of discussion was clarification of the description and purpose of changes discussed in our License Change Request #83-14 dated September 21, 1984.
The points requiring clarification were as a result of omission, typographical errors or lack of grammatical clarity and are as follows:
- 1.
Under Description of Change -
the deletion of the fixed iodine filter monitor as a containment isolation device was not discussed.
The rationale and description of the change was presented later in the text.
- 2.
Table 4.3-3 was incorrectly referenced as Table 4.3-6 in two places (typographical error).
- 3.
In Table 3.3-6 for both units, the alignment of the applicable modes with the required setpoints for item 2.a.l was confusing.
1 The "less than or equal to twice" background applies to Mode 6, while the ODCM guidance on T.S. 3.3.3.9 applies to Modes 1-5.
8608140109 860808" PDR ADOCK 05000272 p
- Mr. Steven A. Varga 2
8-8-86
- 4.
In Table 3.3-6, the High Range Containment Monitors should be labeled as R44 A&B, not just R44.
- 5.
In Table 3.3-6, the measurement range is quoted as 1-104 mR/hr for R46 and 1-106 cpm for RlS.
Mr. Lee asked whether or not this meets the NUREG-0737 range requirements in uCi/cc.
When the ranges are converted to uCi/cc, they meet the NUREG-0737 requirements.
- 6.
Mr. Lee asked to where the condenser air ejectors discharged.
He was informed that they discharged into the plant ventilation and that effluents are further monitored in the vent ducts.
- 7.
On page 2, paragraph two of our text submittal, Mr. Lee was confused by our reference to the containment monitors as "effluent" monitors.
This section of our text lacked clarity.
We intend to set the containment process monitors (llA and 12A) at levels "equivalent" to Technical Specification (ODCM) levels to isolate containment.
These monitors are not primary effluent monitors.
The Rl6 and R41 monitors serve this purpose.
In summary, these points were clarified and the USNRC concurs with these changes.
If we can be of any further assistance in this matter, please do not hesitate to contact us.
Sincerely,
Mr. Steven A. Varga C
Mr. Donald c. Fischer Licensing Project Manager Mr. Thomas J. Kenny Senior Resident Inspector Mr. Samuel J. Collins, Chief Project Branch No. 2 DPRP Region 1 Mr. Jay Lee NRC Staff Reviewer 3
8-8-86