ML20237G483

Proposed Tech Spec Page 6,revising Completion Date for SPDS

ML20237G483
Person / Time
Site:	Hope Creek
Issue date:	08/18/1987
From:	Public Service Enterprise Group
To:
Shared Package
ML20237G477	List: ML20237G475 ML20237G483
References
NUDOCS 8708240102
Download: ML20237G483 (1)

Text

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o (13) Safety Parameter Display System (Section 18.2, SSED No. 5) it the erroer of 9odeus d+u remr+ rmm or .Tulv 12.1988 Prfor to{jg}]{--;-h;-- the first refueling outage /PSEAG 'shal1W

. _ _ _ _ - _ _ . . ._  ; m aa ;a cc; as, m, ,. 2 w g add the following parameters to the SPOS and have.them operational:

1' j a. Primary containment radiation l

b. Primary containment. isolation status

! c. Combustible gas concentration'in primary containment

d. Source range neutron flux L D. The facility requires exemptions.from certain requirements of 10 CFR Part 50 and 10 CFR Part 70. An' exemption from the criticality alarm require-ments of.10 CFR 70.24 was granted in Special Nuclear Material License No.

'1953, dated August 21, 1985. This exemption is described in Section 9.1 of Supplement No. 5 to the_SER. This previously granted exemption is continued in this operating license. An exemption from certain require-lL ments of Appendix A to 10 CFR Part 50, is described in Supplement No. 5 to the SER. .This exemption is a schedular exemption to the requirements of General Design Criterion 64, permitting delaying functionality of the Turbine Building Circulating Water System-Radiation Monitoring System until-5 percent power for local indication, and until 120 days after fuel load for control room indication (Appendix R of SSER 5). Exemptions from certain requirements of Appendix d to 10 CFR Part 50, are described in Supplement No. S to the SER. These include (a) an exemption from the requirement of Paragraph III.D.2(b)(ii) of Appendix J, exempting overall containment air lock leakage testing unless maintenance has been per-formed on the air lock that could affect air' lock sealing capability (Section 6.2.6 of SSER 5); (b) an exemption from the requirement of Paragraph III.C.2(b) of Appendix J, exempting main steam isolation valve leak-rate testing at 1.10 Pa-(Section 6.2.6 of SSER 5); (et an exemption from Paragraph III.D.3 of Appendix J, exempting Type C testing on traversing incore probe system shear valves (Section 6.2.6 of SSER 5);

(d) an exemption from Paragraph III.D.2(a) of Appendix J, exempting Type C testing for instrument lines and lines containino excess flow check valves Section 6.2.6 of SSER 5); and (e) an exemption from Paragraph III.C.2 a) of Appendix J, exempting Type C testing of themal relief valves Section 6.2.6 of SSER 5). These exemptions are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. These exemptions are hereby granted. The special circumstances reaarding each exemption are identified in the referenced section of the safety evaluation report and the supplements thereto. These exemptions are granted pursuant to.

10 CFR 50.12. With these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission.

8708240102 870918 PDR ADOCK 050003S4 P PDR

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