ML18092B533

Application for Amend to License DPR-70,incorporating Facility Attachment 13 to Us/Iaea Safeguards Agreement Into Unit 1 Ol.Fee Paid

ML18092B533
Person / Time
Site:	Salem
Issue date:	04/20/1987
From:	MCNEILL C A Public Service Enterprise Group
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML18092B534	List: ML18092B533 ML18092B535
References
LCR-87-04, LCR-87-4, NLR-N87048, NUDOCS 8704290159
Download: ML18092B533 (7)

Text

{{#Wiki_filter:Public Service Electric arid Gas Company

• Corbin A. McNeil!, Jr. Senior Vice President

-Nuclear Public Service Electric and Gas Company P.O. Box236, Han cocks Bridge, NJ 08038 609 339-4800 April 20, 1987 NLR-N87048 LCR 87-04 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 REQUEST FOR AMENDMENT FACILITY OPERATING LICENSE DPR-70 SALEM GENERATING STATION -UNIT NO. 1 '* In accordance with the Atomic Energy Act of 1954, as amended and the regulations thereunder, we hereby transmit copies of our request for amendment Facility Operating License DPR-70 for Salem Generating Station, Unit No. 1. The proposed amendment requests incorporation of the Facility, Attachment No. 13 to the US/IAEA Safeguards Agreement into the Salem Unit 1 Facility Operating License DPR-70. Enclosed is a check in the amount of $150.00 as required by 10 CFR 170.21. Please ensure that the IAEA is billed for the $150.00 and that amount subsequently reimbursed to PSE&G. Pursuant to the requirements of lOCFRSD.91, a copy of this request for amendment has been sent to the State of New Jersey as indicated below. This submittal includes one (1) signed original and thirty-seven (37) copies. Should there be any questions regarding this matter, please feel free to contact us. 8704.290159 870420 PDR ADOCK 05000272 p PDR Attachment Sincerely, Lf,-{:,e l I I !:!. .2 Document Control Desk C Mr. D. c. Fischer Licensing Project Manager Mr. T. J. Kenny Senior Resident Inspector 2 Director, Bureau of Radiation Protection Department of Environmental Protection 380 Scotch Road Trenton, NJ Regional Administrator, Region I u. s. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 4/20/87 '* STATE OF NEW JERSEY COUNTY OF SALEM ) ) ) Ref: LCR 87-04 SS. Corbin A. McNeill, Jr., being duly sworn according to law deposes and says: I am Vice President of Public Service Electric and Gas Company, and as such, I find the matters set forth in our letter dated April 20, 1987, concerning Facility Operating License DPR-70 for Salem Generating Station, is true to the best of my knowledge, information and belief. and !Jefore me this :p?o/;( . day of / , 1987 uladdw . :*Notary Public of New Jersey DEl.ORJSD.ffADDEN My expires on

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• . PROPOSED CHANGE TO THE FACILITY OPERATING LICENSE SALEM GENERATING STATION -UNIT 1 Description of Change LCR 87-04 Page 1 of 1 The proposed change requests modification of Facility Operating License DPR-70 to incorporate Attachment 1 (the Facility Attachment No. 13, dated October 1, 1986 to the US/IAEA Safeguards Agreement) along with clarifications as identified in Attachment 2 (Salem Nuclear Generating Station, Unit 1 (SNG Sl) IAEA Safeguards License Conditions, Revised) into the license. Reason for Change This change is necessary per the requirements of 10 CFR 75.8. Significant Hazards Consideration It has been determined that this change request involves no significant hazards consideration under the provisions of 10 CFR 50.92. The proposed change is administrative in nature and as such conforms to Example 1 of 49 FR 14870. The proposed amendment implements an IAEA Safeguards inspection program and does not in any way effect the design bases or operation of the facility.

The purpose of the IAEA safeguards inspection is to permit the IAEA to verify that special fissionable material at the facility is not withdrawn (except as provided in the US/IAEA Safeguards Agreement) from the facility while such material is being safeguarded under the agreement. As such, the proposed amendment would not: (1) involve a significant increase in the probability or consequence of an accident previously evaluated1 or (2) create the probability of a new or different kind of accident from any accident previously evaluated1 or (3) involve a significant reduction in a margin of safety. Therefore, the propose amendment does not constitute a significant hazards consideration. Salem Nuclear Generating Station, Unit 1 (SNGS 1) IAEA Safeguards License Conditions REVISED 1. Incorporation of Facility

Attachment:

0 Pursuant to 10 CFR 75.8, NRC License No. DPR-70 is hereby amended to incorporate by reference Codes 1. through 7. of Facility Attachment No. 13 dated October 1, 1986, to the US/IAEA Safeguards Agreement.

2. Facility Attachment Code 2.2 Notification of the changes referred to in Code 2.2 of the facility attachment is the responsibility of the operating facility.

They can be notified to the NRC with a Concise Note (DOE/NRC Form 740M) or a letter. Notification is required 70 days prior to the event. 3. Facility Attachment Code 3.1.3 & 5.1.2 & 5.2.3 The itemized lists of nuclear material to be provided to the IAEA as of cycle shutdown date prior to physical inventory taking are: 1. A complete list of fuel assemblies by ID number at all locations.

2. Reactor and fuel storage maps showing location of fuel by ID number at time of physical inventory taking. 3. A list, by batch, of any other accountable nuclear material, e.g., start-up sources, samples. 4. Facility Attachment Code 3.2.2 Please refer to NRC letter dated May 27, 1986, to Mr. c. A. McNeill from Steven A. Varga which spells out timeliness and procedures for notification under this code. 5. Facility Attachment Code 5.1.1 & 6.1.1 The statement "when calculated" means at least as often as required on page 2 of NUREG/BR-0006 Revision 2 or more often, at your option, if you calculate burn up more than every six months. 6. Facility Attachment Code 6.1.1 & 6.1.2 The phrase "as specified in relevant paragraphs of Code 10" is a requirement on the U.S. All of the paragraphs in the US.IAEA Agreement that require a report from the U.S. to the IAEA based on source data from an operating facility have been incorporated into NUREG's BR-0006 and 0007 so that the

-, NRC may collect the needed data for transmittal to the IAEA. PSE&G should follow these NUREGs precisely in reporting inventory changes. A complete response to the reporting instructions in the NUREGs will satisfy the requirements specified in Code 10. 7. Facility Attachment Code 6.2.2 The phrase "precise forecasts" means best estimates. These required concise notes should be dispatched to the NRC at least 40 days in advance of a projected 6 month operational programming.

8. Facility Attachment Code 6.3.1 & 6.3.2 See response to Code 6.1.1 and 6.1.2 above. 9. Facility Attachment Code 7.9 The specific facility health and safety rules and regulations to be observed by the Agency's (IAEA) inspectors, as specified in Paragraph 54 of the design information as of October 10, 1986, provided by the U.S.A. mean: 0 0 0 0 Agency inspectors who have previously visited the facility will be informed as necessary at the time of entry into the facility of health and safety rules and ad hoc rules as might be required in view of a special situation that has occurred at the facility since the inspector's last visit to the facility.

The briefing will be of a short duration, not to exceed 30 minutes, covering topics deemed relevant by the licensee. Agency inspectors who have not previously visited the facility will be informed a811ecessary at the time of entry into the facility of health and safety rules and ad hoc rules as might be required in view of a special situation that has occurred at the facility. The briefing will be of an appropriate duration, not to exceed three hours, and consist of topics deemed relevant by the licensee. In either case, the licensee should take into account the Agency inspector's prior training, expertise and experience. In neither case shall the Agency inspector be subject to any form of evaluation or testing by facility representatives or representatives of the U.S. Government. For health and safety reasons, Agency inspectors will be escorted by qualified facility personnel at times deemed appropriate by the licensee.

10. Termination 0 Pursuant to the provisions of 10 CFR 75.41, the Commission will inform the licensee, in writing, when its installation is no longer subject to Article 39(b) of the principle text of the US/IAEA Safeguards Agreement.

The IAEA Safeguards License Conditions incorporating Code 7. of the Facility Attachment as part of NRC License No. DPR-70 will be terminated as of the date of such notice from the Commission. However, since the IAEA may elect to maintain the licensee's installation under Article 2(a) of the Protocol, provisions equivalent to Codes 1. through 6. of the Facility Attachment (with possible appropriate modifications) may still apply, and accordingly all other IAEA Safeguards License Conditions to NRC License No. DPR-70 will remain in effect until the Commission notifies the licensee otherwise. If this option is not selected by the IAEA, the Commission will then notify the licensee that all License Conditions pertaining to the US/IAEA Safeguards Agreement are terminated.}}