ML20083G442
| ML20083G442 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 12/22/1983 |
| From: | Musolf D NORTHERN STATES POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-TM NUDOCS 8401060230 | |
| Download: ML20083G442 (1) | |
Text
+wy Northem States Power Company 414 Nicollet Man December 22, 1983
$","p',*oQs,"f"3j'*$#U' Director Office of Nuclear Reactor Regulation U S Nuclear Regulatory Commission Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLA!Tr Docket Nos. 50-282 License Nos. DPk-42 50-306 DPR-60 Post Accident Sampling System (NUREG-0737, Item II.B.3)
Reference:
(a) Letter from J R Miller (NRC) to D M Musolf (NSP), " Post Accident Sampling System (NUREG-0737, Item II.B.3)
This letter is in response to those request.; made in Reference (a) to provide a schedule for the submittal of a revised procedure for estimating the extent of core damage and confirmation that heat tracing will be installed on the containment sampling lines by June 30, 1984.
The current schedule of the Westinghouse Owners Group Subcommittee has slipped from December, 1983 to February, 1984 for providing core damage assessment methodology. Mr J A-Norris of the NRC was informed by Mr J J Sheppard, Chairman of the Westinghouse Owners Group (WOG) on November 4, 1983 of the delay.
Northern States Power Company will use the core damage assessmeat methodology as a reference upon issuance by the WOG in February, 1984. Formal incorporation into our Emergency Plan Implementing Procedures will be completed within 120 days af ter receipt of the WOG methodology.
The heat tracing will be installed on the containment air sampling lines from the shield building to the sampling condenser by June 30, 1984.
As a point of clarification on page 4 of the Safety Evaluation contained in Reference (a) it was stated that training would be conducted monthly, when in fact training is done annually. The basis for annual training as was discussed and agreed to during a Telecon with Mr F Witt and D DiIanni of the NRC on June 10, 1983 is that a majority of Reactor Coolant Post Accident Sampling System is operated for plant routine sampling.
If you have any questions concerning this submittal or if additional infor-mation is necessary, please contact us.
k
- 1 D M Musolf Manager - Nuclear Su p rt Services DMM/ TAP / dab c: Regional Administrator-III, NRC Project Manager, NRC
{g Resident Inspector, NRC G Charnoff g401060230 831222 PDR ADOCK 05000282 p