ML13310B123
| ML13310B123 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 12/27/1983 |
| From: | Medford M Southern California Edison Co |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML13310B125 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TAC-44478, TASK-2.B.3, TASK-TM NUDOCS 8312290291 | |
| Download: ML13310B123 (3) | |
Text
Southern California Edison Company P. 0.
BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD. CALIFORNIA 91770 M.O. MEDFORD TELEPHONE MANAGER, NUCLEAR LICENSING December 27, 1983 (213) 572-1749 Director, Office of Nuclear Reactor Regulation Attention:
Mr. D. M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Gentlemen:
Subject:
Docket No. 50-206.
Post-Accident Sampling Capability San Onofre Nuclear Generating Station Unit 1
References:
- 1. Letter, K. P. Baskin, SCE, to D. M. Crutchfield, NRC, NUREG-0737, Item II.B.3 -
Post-Accident Sampling Capability, Post-Implementation Review, December 3, 1982
- 2. Letter, D. M. Crutchfield, NRC, to R. Dietch, SCE, TMI Action Plan Item II.B.3 - Post-Accident Sampling System, September 1, 1983
.3. Letter, D. M. Crutchfield, NRC, to R. Dietch, SCE, NUREG-0737 Item II.B.3 -
Post-Accident Sampling System, June 30, 1982
- 4. Letter, R. Dietch, SCE, to H. R. Denton, NRC, Docket Nos. 50-361 and 50-362, San Onofre Nuclear Generating Station, Units 2 and 3, April 14, 1983 Reference 1 provided you with the information to perform a post-implementation review of the subject topic for San Onofre Nuclear Generating Station, Unit 1. The evaluation enclosed with Reference 2 indicated that there were open items regarding Criteria 2 and 10 and requested that we respond to the open items. In response to that request the following information is provided for the San Onofre Unit 1 Post-Accident Sampling System (PASS).
It is formatted to document the inquiry and response.
NRC Inquiry: Criterion 2 requires a procedure for relating radionuclide concentrations to core damage. SCE has not yet committed to develop this type of procedure for San Onofre Unit 1.
8312290291 831227 PDR ADOCK 05000206 P
PDR_
Mr. D.
December 27, 1983
Response
The procedure for core damage assessment at San Onofre Unit 1 will be developed prior to return to power from the current outage. The procedure will incorporate the Westinghouse Owner's Group Core Assessment guidance as it can be applied to San Onofre Unit 1. The procedure will be used, and the core condition established, by the technical support group in the Emergency Operations Facility. The procedure that currently exists for this function, provided as Enclosure 1 to this letter, applies only to San Onofre Units 2 and 3, but the format and results in the San Onofre Unit 1 procedure will be very similar in nature.
NRC Inquiry: The clarification to Criterion 10, as presented in References 2 and 3, states that the licensee should demonstrate the applicability of the procedures and instrumentation in the post-accident water chemistry and radiation environment. The sample ranges and accuracies should be provided.
Response
The sample ranges for the San Onofre Unit 1 PASS were provided to you in our response to Criterion 2, on page 4 of Reference 1. The information is repeated in Enclosure 2 to this letter for purposes of completeness. The information contained in Enclosure 2 (1) corrects some typographical errors and (2) deletes some information which was not essential.
The demonstration conducted for the San Onofre Units 2 and 3 PASS, documented in Reference 3, yielded data on the PASS accuracy that is applicable for San Onofre Unit 1. As you know, San Onofre Unit 1 has a Combustion Engineering PASS which is identical to that of San Onofre Units 2 and 3. Modifications were necessary during the start-up of the San Onofre Units 2 and 3 PASS, and the extent to which these modifications must be implemented for the San Onofre Unit 1 PASS, will be discussed with the NRC staff prior to return to power from the current outage. The results of the previously discussed demonstration are provided as Enclosure 3 to this letter. The surveillance accuracy requirements that will be applied to the San Onofre Unit 1 PASS are provided as Enclosure 4 to this letter. The procedures that implement the surveillance and operating requirements, will be developed and the staff trained, prior to return to power from the current outage. These procedures for San Onofre Unit 1 will be consistent with the Post-Accident Sampling (PAS) Program which was approved by the NRC for use at San Onofre Units 2 and 3.
It should be noted that we have revised our response to Criterion 10 of Reference 1, which indicated that retraining would be conducted at a frequency of every six months.
Subsequent PAS Program development for San Onofre Units 2 and 3
Mr. D.
December 27, 1983 specified retraining frequency to be every twelve months. The retraining frequency of every twelve months, in addition to the operation of the PASS during routine system surveillances will provide an adequate opportunity for demonstrating system and operator reliability. This retraining frequency is included in the San Onofre Nuclear Generating Station, Units 1, 2 and 3 PAS Program.
The above information should satisfy the staff's request. If you have any questions or require any additional clarification, please let me know.
Very truly yours, Enclosures