ML18092B215
| ML18092B215 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 07/14/1986 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| NFU-86-236, NUDOCS 8607220394 | |
| Download: ML18092B215 (4) | |
Text
Public Service Electric and Gas*
Company Corbin A. McNeill, Jr.
Vice President -
Public Service Electric and Gas Company P.O. Box236, Hancocks Bridge, NJ 08038 609 339-4800 Nuclear July 14, 1986 Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue
- Bethesda, MD 20014 Attention:
Gentlemen:
Mr. Steven A.
Varga, Director PWR Project Direct~rate 13 Division of PWR Licensing A NFU 86-236 REVIEW OF PROPOSED INTERNATIONAL ATOMIC ENERGY AGENCY CIAEA>
FACILITY ATTACHMENT SALEM UNIT 1 DOCKET NO.
50-272 Pursuant to the request in a recent undated NRC letter ( D.
C.
Fischer>, PSE&G has reviewed the proposed IAEA facility attachment for Salem Unit 1.
This review included a meeting on July 9, 1986, between PSE&G staff and NRC staff CE.
Sparks> to discuss the contents1 of the proposed facility attachment.
In response to the letter, PSE&G does nbt desire to withhold from the public under 10CFR2.790 any of the types of information found in the proposed attachment.
As agreed in the meeting on July 9, we have prepared a list of requested c~arifications <Attachment 1> for the proposed facility codes to be included in the NRC's interpreting statements.
It is our understanding that these statements will accompany the final facility attachment.
In addition, Attachment 2 presents a list of changes to the information in the Salem Unit 1 IAEA design information questionnaire C DIQ>.
As noted in Attachment 2, these changes should also be included in the IAEA facility attachment.
As requested by Mr. Sparks, the appropriate material description codes for the two gamma-metric detectors qualifying as "small
.~ 8607220394 806500706~72 PDR ADOCK F
PDR _
Mr. Stevsn A.
Varga 7/14/86 quantities of nuclear material" are "Q OA" for non-irradiated and "Q OH" for irradiated detectors.
If you have any questions, please contact E.
S. Rosenfeld at
( 609) 339-4723.
C Mr. Donald C. Fischer Licensing Project Manager Mr.
Thomas J. Kenny Senior Resident Inspector Sincerely, Willard B.
Brown, Chief Safeguards Material Licensing and International Activities Branch Office of Material Safety and Safeguards, NRC
CODE NUMBER
- 2. 2
- 3. 1. 3,
- 5. 1.2 &
- 5. 2. 3
- 3. 2. 2
- 5. 1. 1
- 6. 1. 1,
- 6. 1. 2
- 6. 2. 2
- 6. 3. 1 &
- 6. 3. 2 ATTACHMENT
~~1 REQUESTED CLARIFICATIONS OF SALEM UNIT 1 PROPOSED IAEA FACILITY ATTACHMENT CLARIFICATION REQUESTED NFU 86-236 Please provide clarification of how much advance notice is required from PSE&G in reporting these items.
Please clarify which of these notifications are NRC responsibilities and which are PSE&G responsibilities.
Please clarify that an itemized list of nuclear material as of cycle shutdown date prior to physical &
inventory taking in addition to reactor and fuel storage location maps showing new locations of fuel at time of physical inventory taking meets the requirements for the "itemized" lists referred to in these codes.
Please clarify how much advance notification is required.
Please clarify notification requirements in the event of an emergency or an accidental breaking of a seal or interference with equipment.
Please clarify what is meant by the phrase "When calculated".
Please clarify what is meant by phrase "as specified in relevant paragraphs of Code 10".
Please clarify what is meant by the phrase "when calculated".
In addition, please clarify timing and frequency requirements for PSE&G reporting of inventory changes.
Please clarify that "precise forecasts" means best estimates.
Please clarify how much advance notice is required for PSE&G to notify the NRC.
Please clarify what is meant by phrase "as specified* in
~elevant paragraphs of Code 10, General Part".
NFU 86-236 ATTACHMENT 2 CHANGES TO SALEM NUCLEAR GENERATING STATION UNIT 1 IAEA DESIGN QUESTIONNAIRE CDIQ) INFORMATION JULY 1986 DIQ Paragraph Number 14 37 REVISED DATA Change rated thermal output and electrical output data to:
Gross Thermal Gross Electrical Net Electrical Station Use 3411 MWt*
1158 MWe 1115 MWe 43 MWe Change interval between refuelings from 15-17 months to 15-19 months.*
Please update corresponding values in Code 1. 4 of the proposed IAEA facility attachment.