ML20099C617
| ML20099C617 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/31/1984 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20099C616 | List: |
| References | |
| NUDOCS 8411190606 | |
| Download: ML20099C617 (3) | |
Text
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i SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 102 TO FACILITY OPERATING LICENSE NO. DPR-50 METROPOLITAN EDIS0N COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVAhIA ELECTRIC COMPANY GPU NUCLEAR CORPORATION THREE MILE ISLAND NUCLEAR STATION, UNIT N0. 1 DOCKET NO. 50-289 Introduction In a letter dated June 4, 1984, the licensee has requested four changes to the
. Technical Specifications (TSs), as follows:
1.
Revise TS 3.6.7 to state "... bring the reactor to HOT SHUTDOWN within seven (7) days."
2.
Revise TS Table 4.1-1, Instrument Surve111anc'e Requirements, Item 2, Control Rod Drive Trip Breaker, by adding'the remark " Includes shunt trip features."
3.
Delete TS 6.15, Environmental Qualification.
4.
Replace TS 6.16, Iodine Monitoring Program, with a new Section 6.16, Post-Accident Sampling Programs, to include programs for Iodine and Particulate Sampling, Reactor Coolant Sampling and Containment Atmosphere Sampling.
We discussed the proposed changes with the licensee, and by the licer.see's letter dated August 8,1984. the proposed changes were revised to improve clarity as follows:
a)
TS Table 4.1-1, the additional remark was changed to " Includes independent testing of shunt trip and undervoltage trip features."
b)
TS 6.15 was revised to include in the title, "...(II.B.3 and II.F.1.2)";
in line 1, "...to accurately sample and analyze..."; in line 4, "1. Iodine and Particulate Sampling."
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a Evaluation 11.
The revision which changes " HOT STANDBY" to " HOT SHUTDOWN"_is obviously a correction of a clerical error because the reactor is already.
permitted to be in HOT STANOBY mode before entering.the action. statement.
that requires bringing the reactor to a safer node if the hydrogen recombiner'is inoperable.
Accordingly, we find this change acceptable.
2.
The revision to Table 4.1-1, as modified by the licensee's letter dated.
-August 8, 1984, is a change that resulted-from our review of Item'4.3 of Generic Letter 83-28 dated July 8,1983, " Required Actions Based on Generic. Implications of the Salem ATWS Events."
In our Safety Evaluation of Item 4.3, "R4 actor Trip System Reliability - Automatic 1
Actuation of the Shunt Trip Attachment for B&W Plants," dated July 17, 1984, welconcluded that the licensee should revise the TSs to specifically require independent testing of the shunt trip and undervoltage trip features. This proposed change meets the NRC staff's requirements on Item 4.3 and therefore is acceptable.
- 3..
The.TSs on Environmental Qualification, Section 6.15,- refer to actions to be completed in 1980 and 1982 that have been superseded by regulations under 10 CFR 50.49, " Environmental qualification of-i electrical equipment...". Therefore, we concur in the' licensee's assessment that this is an administrative change that updates the TSs, and we find this proposed change acceptable.
4.
The current TS 6.16 includes only iodine monitoring.
The proposed TS 6.16 wi11' expand this section to include other post-accident monitoring programs, namely particulate sampling, reactor coolant sampling and containment atmosphere sampling.
The need to revise the TSs on these issues was addressed in the NRC staff's Generic Letter (GL 83-37), sent to All Pressurized Water Reactor Licensees, dated November 1,1983.
i Staff guidance for preparation of TSs for NUREG-0737 items scheduled-after December 31, 1981, was included as Attachment 1 to GL 83-37, i
including Item (2) Post-Accident Sampling (II.B.3) and Item (5) Sampling and Analysis of Plant Effluents (II.F.1.2). The licensee has addressed 4
these two items in the TS change request dated June 4, 1984.
l The proposed TS follows GL 83-37 guidance by referencing the programs in the administrative controls section of the TS and including the suggested details provided in GL 83-37. Therefore, we find this proposed change acceptable.
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Environmental Consideration This amendment involves a change in the use of a facility component located within the restricted area as defined in 10 CFR Part 20.
This amendment also relates to changes in recordkeeping, reporting, or administrative procedures or requirements.
The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public comment on such finding.
Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) and (10).
Pursuant to 10 CFR 51.22(b),
no environmental impact statement or environmental ' assessment need be prepared in connection with the issuance of this amendment.
Conclusion We have concluded, based on the considerations discussed above, that: (1) there is reasonable _ assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted.in compliance with the Commission's regulations an'd the issuance of this amendment will not be inimical to the ccmmon defense and security or to the health and safety of the public.
Dated: October 31, 1984 The following NRC personnel have contributed to this Safety Evaluation:
- 0. Thompson m
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