ML18093A333
| ML18093A333 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/28/1987 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML18093A334 | List: |
| References | |
| NLR-N87151, NUDOCS 8709030511 | |
| Download: ML18093A333 (3) | |
Text
Public Service Electric and Gas Company Corbin A. McNeill, Jr.
Senior Vice President -
Nuclear Public Service Electric and Gas Company P.O. Box236, Han cocks Bridge, NJ 08038 609 339-4800 August 28, 1987 NLR-N87151 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
RADIOACTIVE EFFLUENT RELEASE REPORT -
22 SALEM GENERATING STATION DOCKET NOS. 50-272 AND 50-311 In accordance with Section 6.9.1.11 of Appendix A to the Operating Licenses for the Salem Generating Station, Unit Nos. 1 and 2, Public Service Electric and Gas Company (PSE&G) hereby transmits one copy of the semi-annual Radioactive Effluent Release Report, RERR-22.
This report summarizes liquid and gaseous releases and solid waste shipments from the Salem Generating Station for the period January 1 through June 30, 1987.
Additionally, please find one copy of the revised Offsite Dose Calculation Manual (ODCM).
A summary of these changes to the ODCM and their rationale is provided in Attachment A.
Changes to the document are delineated by vertical lines in the margin of the text.
The majority of these changes are administrative.
Should you have any questions regarding this submittal, please feel free to contact us.
Attachments 8709030511 870828-------,
kDR ADOCK 05000272 PDR Sincerely,
Document Control Desk 2
C Mr. w. T. Russell, Administrator USNRC Region I Mr. D. C. Fischer USNRC Licensing Project Manager Mr. T. J. Kenny USNRC Senior Resident Inspector Dr. T. E. Murley, Director Off ice of Nuclear Reactor Regulation Washington, DC 20555 Mr. D. M. Scott, Chief Bureau of Nuclear Engineering Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628 8-28-87
ATTACHMENT A SALEM OFFSITE IX>SE CALCULATION MANUAL
SUMMARY
OF CHANGES The changes to the Salem Generating Station Offsite Dose Calculation Manual consisted of the following:
- 1)
Delete Fe-59, the word "quarterly" and addition of reference to Technical Specification 3.11.1.1 from the note on Page 4.
RATIONALE:
Fe-59 is not required for composite analysis (Reference Technical Specification 3.11.1.1 Table 4.11-1).
Also, the composite analysis are
.both quarterly and monthly depending on the radionuclide.
To avoid confusion the time reference was deleted.
- 2)
Updating the dose factors for Antimony 124 and 125 for the grass-cow-milk pathway (Pages 52-55).
RATIONALE:
These factors were conservative stable element transfer factors.
They have been updated based on transfer factors from Regulatory Guide 1.109 (Revision 0).
- 3)
Addition of 1985 and 1986 liquid release data for Appendices A, Band C (Pages A-3 to A-5, B-2, B-5, and C-3).
RATIONALE:
To ensure that effective MPC factors and major dose contributors by radionuclide are consistant with current default parameters within the ODCM.
- 4)
Revise the reference from the Salem Generating Station Emergency Plan EPIV-III to Emergency Plan Implementation Procedures on Page 27.
RATIONALE:
For completeness These modifications were used to generate the Radiological Effluent Release Report (#22) for the first half of 1987.