ML20237K031

Forwards RERR-3, Semiannual Radioactive Effluent Release Rept,Jan-June 1987 & Rev 8 to Offsite Dose Calculation Manual

ML20237K031
Person / Time
Site:	Hope Creek
Issue date:	08/28/1987
From:	Corbin McNeil Public Service Enterprise Group
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20237K032	List: ML20237K031 ML20237K055 ML20237K067
References
NLR-N87150, NUDOCS 8709040165
Download: ML20237K031 (4)

Text

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Public Service Electric and Gas Company Corbin A. McNeill, Jr. Pubi 3ervice Electric and Gas Company P.O. Box 236. Hancocks Bridge, NJ 08038 609 339-4800 Senior Vice President -

' Nuclear August 28, 1987 NLR-N87150 United States. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

RADIOACTIVE-EFFLUENT RELEASE REPORT - 3 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 l Ja accordance with Section 6.9.1.7 of Appendix A to the Operating License for the Hope Creek Generating Station (HCGS), Public Service Electric and Gas Company (PSE&G) hereby transmits one

, copy of the semi-annual Radioactive Effluent Release Report, RERR-3. This report summarizes liquid and gaseous releases and solid waste shipments from the HCGS for the period January 1 througn June 30, 1987.

Additionally, please find one copy of the revi Ei Offsite Dose Calculation Manual (ODCM). -A summary of the 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 i text. The majority of these changes are administrative.

Should you have any questions regarding this submittal, please ,

feel free to contact us.

Sincerely, J

Attachments  ;

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8709040165 870028-PDR ADOCK 05000354 R ppg y6 %

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Document Control Desk 2 8-28-87 C Mr. W. T. Russell, Administrator USNRC Region I Mr. G. W. Rivenbark USNRC Licensing Project Manager Mr. R. W. Borchardt >

USNRC Senior Resident Inspector Dr. T. E. Murley, Director Office 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 i

r ATTACHMENT A HOPE CREEK OFFSITE DOSE CALCULATION MANUAL

SUMMARY

OF CHANGES The changes to the Hope Creek.Offsite Dose Calculation Manual consisted of the following:

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1) Typing correction on Page 2 correcting the referenced cooling tower blowdown monitor number from RE4817 to RE8817, typing {

correction on Page 13 correcting.the referenced South Plant i Vent monitor from RE4873 to RE4875 and the North Plant Vent monitor from RE4873 to RE4573.

RATIONALE: For completeness.

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2) Addition of revision numbers and dates on Pages 38-59 and I~ ' Appendices.

RATIONALE: For completeness.

3) Deletion of Fe-59, the word " quarterly" and addition of reference to Technical Specification 3.11.1.1 from the note on Page 5.

RATIONALE: Fe-59 is not required for composite analysis (Reference Technical Specification 3.11.1.1 Table 4.11-1).

4) Change the effective MPC from 1.4E-5 uCi/ml to 1.9E-5 uCi/ml )

on Pages 6 and A-5 and correct the MPC concentrations in j Table A-1.

RATIONALE: Some of the MPC concentrations used to calculate -

the effective MPC in Appendix A Table A-1 were incorrect'(Na-24, P-32, Cr-51, Fe-59, Co-58, co-60, Nb-95,' Tc-99m). These numbers were corrected and the effective MPC recalculated.

This factor is used to provide default monitor setpoints.

5) The default monitor setpoints for RE4861 and RE8817 in Table 1-1 (Page 39).

RATIONALE: To reflect the change in the effective MPC which is used to calculate these setpoints. ,

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6) Updating the dose factors for Antimony 124 and 125 for the

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grass-cow-milk pathway (Pages 52-55). i RATIONALE: These factors were conservative stable element  ;

transfer factors. They have been updated based i on transfer factors from Regulatory Guide 1.109  ;

(Revision 0). 1 1

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7) LAddition.of a near field dilution factor of 0.05 to the liquid effluent dose calculation (effecting Pages 8, 9, 10, 11, B-3,.B-4,.B-5).

RATIONALE: The' dose calculation for liquid releases were too conservative and caused unnecessary processing of liquid releases. Based on NUREG-0133 Section 4.1

.an' analysis was performed and a near field dilution factor was calculated. The factor of 0.05'(described on Page B-4 of the ODCM) is conservative, within NUREG-0133 limits, provides  !

a more representative dose calculation, and cuts I

'back on excessive liquid release processing. )

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8) Change the 31-day dose projection equation from a divider of 1 91 days to a divider of the number of days in the current calendar quarter.

RATIONALE: This provides a more conservative and " ensuing" (from NUREG-0133). equation to determine the need for processing effluents.

These modifications were used to generate th? Hope Creek

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Generating Station Radiological F,ffluent Release Report (#31 for. ,

the first half of 1987. j i

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l PJM:ch Rev. 8 07/29/87 .

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