ML20234B970

Safety Evaluation Supporting Amend 28 to License DPR-73

ML20234B970
Person / Time
Site:	Three Mile Island
Issue date:	06/25/1987
From:	Office of Nuclear Reactor Regulation
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Shared Package
ML20234B936	List: ML20234B933 ML20234B956 ML20234B970
References
NUDOCS 8707060292
Download: ML20234B970 (9)

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Enclosure 2 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION l GPU NUCLEAR CORPORATION METROPOLITAN EDISON COMPANY PENNSYLVANIA ELECTRIC COMPANY q l

l JERSEY CENTRAL POWER & LIGHT COMPANY DOCKET N0. 50-320 THREE MILE ISLAND NUCLEAR STATION UNIT N0. 2 l

1.0 INTRODUCTION

l By letter dated January 27, 1987, GPU Nuclear Corporation (GPUNC)  !

requested the approval of changes to the Technical Specifications of Orerating License No. DPR-73 and provided supporting information for the proposed modifications. Also included was a request to modify the Recovery Operations Plan which will be addressed in separate l l

correspondence. The proposed changes to the Technical Specifications {

redefine the scope of licensee procedures requiring NRC staff review and i

approval prior to implementation. The proposed changes would modify the Administrative Controls section defining the scope of procedures  !

I requiring NRC approval, and the related Limiting Conditions for Operations that make reference to the Administrative Controls section.

2.0 DISCUSSION AND EVALUATION Section 6.8 Technical Specification 6.8.2 requires that the licensee obtain NRC staff approval of detailed operating procedures and changes to procedures that:

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1) directly relate to core cooling, 2) could cause the magnitude of radiological releases to exceed NRC Ifmits, 3) could incr#ase the likelihood of failures in systems important to nuclest safety and radioactivewasteprocessingorstorage,or4)alterthedistribbtionor processing of significant quantities of radioactivity being stored or released through known flow paths.

The licensee proposes to modify the Technical Specificat'fons to require NRC staff approval of only those procedures and changes thereto which alter the distribution- or processing of a quantity of radioactive. \~

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material, the release of which could cause the magnitude of radiological 1 .

releases to exceed the design objectives of 10 'CFR 50 Appehdix I. ',

The March 28, 1979 accident left Three Mile Island Unit 2 incapable of normal operations. Although the reactor was shutdown shortly after the accident, a great deal of uncertainty remained regarding the condition of' plant systems, the extent of nuclear fuel damage, and the best approach for recovery from the accident. As a result of the accident the facMity was severely contaminated and there was the presence of highly s.

contaminated liquids in the reactor building basement and'fr. tanks'in the ,

auxiliary building. The potential impact on public health and sdfety arising from the unique and relatively unknown conditions of the facility resulted in an agency decision to include NRC staff review and approval in the control of certain plant activities. As a result, the requirements of the Technical Specification 6.8.2 were imposed upon tha -

licensee and formally incorporated by the Commission Order of February.

11, 1980 issuing the proposed Technical Specifications to license DPR-73.

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'> 3-This license requirement for detailed NRC review and approval of many operating procedures has been unique to the TMI-2 project. The adequacy of licensee procedures at nuclear power facilities is normally only monitored by the NRC on a periodic audit basis. l L

Cleanup activities have been ongoing for about eight years and the facility is currently in a stable, long-term shutdown mode. Fission product decay has progressed to the point that the decay heat load is less than 10 kilowatts and forced cooling of the reactor core is no l

longer needed. The reactor coolant system is no longer pressurized and 1

the reactor vessel head has been removed from the vessel. The core is covered with water and is maintained subcritical by the presence of boron in the water. Analyses have shown that there is no credible configuration of the core material that could result in a recriticality I

as long as the boron concentration in the water is maintained within the

' current Technical Specification limits. Removal of the damaged core is

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in progress and about 30 percent of the core debris has been removed from ,

l the reactor vessel. The plant is no longer in a potentially unstable 1 l

dynamic situation with the need for 1nmediately available safe shutdown systems to cope with emergencies. Based on the current status of the TMI-2 facility requirements for operability of emergency diesel generators were deleted in an earlier licensing action. Additionally, a great deal of decontamination work has been completed in the reactor building and in the auxiliary and fuel handling buildings. Highly ,

contaminated water resulting from the accident has been processed to remove a large quantity of the radioactive material and much of the resulting waste has been removed from the site for proper disposal, i

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-4 Major defueling related activities are reviewed by the NRC staff and the potential consequences of postulated accidents related to those activities are evaluated by the staff to assure that those activities do rtot poso a risk to the public health and safety. These reviews are documented in docketed safety evaluation reports.

Since the accident, the licensee has implemented a number of major  ;

I management and organizational changes designed to more effectively manage the unique challenge of the post-accident cleanup. These changes have resulted in an organizational structure which places an acceptable emphasis on the safe conduct of cleanup activities with adequate provisions for management review and oversite of facility activities.

The staff's ongoing assessment of the licensee's procedure development and review program indicates that it is working effectively to assure implementation of the Technical Specifications and compliance with regulatory requirements.

Based on the above, the staff concludes that the cleanup activities at the Three Mile Island Unit 2 facility no longer require unique administrative controls for all significant station activities.

Recognizing the current plant conditions it is appropriate to effectively focus NRC attention in the area of procedural controls on only those activities with potential offsite consequences. Thus, the staff concludes that reducing the scope of licensee procedures requiring pre-implementation NRC approval to include only those which involve a quantity of radioactive material the release of which could cause the mag- i nitude of radiological release to exceed the design objectives of 10 CFR 50 l

. 5-Appendix I will not pose additional risk to the public health and safety. 'i The staff therefore concurs with the requested change. )

The staff will continue to review the adequacy of all licensee procedures and the licensee's compliance with regulatory requirements through the routine NRC inspection program. This includes onsite inspection of licensee activities, and periodic technical review and evaluation of licensee procedures.

Section 3.1.1.2 Technical Specification 3.1.1.2 requires that action be taken in accordance with procedures approved pursuant to Technical Specification 6.8.2 if reactor coolant system boron concentration or temperatures are outside of specified limits.

The licensee proposes to modify the specification by eliminating the reference to Technical Specification 6.8.2 and by requiring corrective i action in accordance with the currently existing Technical Specification 3.0.3.

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The staff has concluded that since the corrective action and reporting requirements of Technical Specification 3.0.3 are already applicable even with the use of NRC approved procedures, the modifications do not allow a reduction in the actions required to maintain safe stable conditions and are in accord with the reduction in the scope of procedures requiring NRC ,

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scope of procedures requiring NRC approval as previously discussed.

Implementing procedures will still be required per existing codes and standards imposed by other regulatory requirements. The staff therefore concurs with the requested changes.

Sections 3.9.2 and 3.9.4 These specifications require maintaining the Spent Fuel Pool "A" and Fuel Transfer Canal water levels in accordance with NRC approved procedures.

The proposed modification would eliminate the requirement for NRC approval of the applicable procedures. However, it would impose the current quantitative water level limits contained in the presently approved procedures by reference to the Recovery Operations Plan.

Changes to the Recovery Operations Plan require NRC review and approval.

The staff has determined that the modification would not result in any less conservative limits than are presently in place and approved by the staff and therefore concurs with the requested change.

3.0 CONTACT WITH STATE OFFICIAL The NRC staff has contacted, by telephone, the Director, Bureau of Radiation Protection, Department of Environmental Resources, Commonwealth of Pennsylvania, concerning the proposed determination of no significant hazards consideration. No objection to the proposed action was voiced.

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staff approval as discussed previously. The staff therefore concurs with the requested change.

Sections 3.4.1 and 3/4.4.1 These specifications only require that the reactor coolant system be operated in accordance with NRC approved procedures, and state that the basis for these specifications is to ensure adequate core cooling.

The licensee proposes to delete these specifications.

Deletion of these specifications will not alter the limits of reactor coolant system parameters imposed by other existing Technical Specifications. It will only delete the requirement for NRC approval of Technical Specification implementing procedures. Therefore, for the reasons stated previously, there is no longer a need for NRC staff, approval of procedures that may affect core cooling. The staff therefore concurs with the requested changes.

Sections 3.4.9.2, 3.8.2.1, and Table 6.2-1 These specifications contain a reference to specification 6.8.2. The 4 j

licensee proposes to delete the references to the procedure review J l

J requirements of specification 6.8.2.

The proposed modifications do not result in any change to the requirements imposed on the licensee other than the reduction's in the

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4.0 ENVIRONMENTAL CONSIDERATION

We have determined that the amendment does.not authorize a change in effluent types or total amounts and will not result in a significant increase in individual or cumulative occupational radiation exposure.

The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration (52FR16947), and no public comments or requests for a hearing were received. Accordingly, the amendment meets the eligibility criteria for categorical exclusion setforthin10CFR51.22(c)(9). 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.

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5.0 CONCLUSION

l Based upon our evaluation of the proposed changes to the TMI-2 Technical Specifications the staff finds that the licensee's request is acceptable.

We have further 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

-9 (2) such activities will be conducted in compliance with the Commission's regulations and the implementation of this change will j not be inimical to the common defense and security or to the health and safety of the public. .

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UNITED STATES g NUCLEAR REGULATORY COMMISSION

[ E WASHINGTON, D. C. 20555 g,

a June 25,1987

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Docket No. 50-320 MEMORANDUM FOR: Sho11y Coordinator Office of Nuclear Reactor Regulation FROM: William D. Travers, Director TMI-2 Cleanup Project Directorate Division of Reactor Projects III/IV/V and.Special Projects i

SUBJECT:

REQUEST FOR PUBLICATION IN BIWEEKLY FR NOTICE - NOTICE OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE General Public Utilities Nuclear Corporation, Docket No. 50-320, Three Mile Island Nuclear Station Unit 2 (TMI-2), Dauphin County, Pennsylvania .

Date of application for amendment: January 27, 1987 Brief description of amendment: The amendment revises the Technical Specifications by redefining the scope of licensee procedures and changes thereto that require NRC staff approval prior to implementation. Only those procedures and changes thereto which alter the distribution or processing of a quantity of radiological material, the release of which could cause the magnitude of radiological releases to exceed the design objectives of 10 CFR 50 Appendix I.

Date of Issuance: June 25,1987 Effective Date: June 25,1987 I

Amendment No.: 28 Facility Operating Licensing No. DPR-73: Amendment revised the Technical Specifications.

Date of initial notice in Federal Register: May 6, 1987 (52 FR 16947) pg73 s453-(5pf7 I

Sho11y Coordinator The Commission's related evaluation is contained in a Safety Evaluation dated June 25, 1987.

No significant hazards consideration comments received: No.

Local Public Document Room Location: State Library of Pennsylvania, Government Publications Section, Education Buf1 ding, Commonwealth and Walnut Street, Harrisburg, Pennsylvania 17126.

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William D. Travers, Director TMI-2 Cleanup Project Directorate Division of Reactor Projects III/IV/V and Special Projects l

DISTRIBUTION Docket file 50-320 TNI-2 HQ file TMI-2 site reading file OGC-Bethesda MMasnik llTravers Sholly Coordinator (Orig & I)

M h1 MM TA:PD42 D:PD42 OGC/Beth MMasnik WTravers LChandler 6/8/87 6/75/87 6/ /87 see attached i

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Sholly Coordinator The Commission's related evaluation is contained in a Safety Evaluation dated

. No significant hazards consideration comments were received.

Local Public Document Room Location: State Library of Pennsylvania, Government Publications Section, Education Building, Commonwealth and Walnut Streets, Harrisburg, Pennsylvania 17126.

William D. Travers, Director TMI-2 Cleanup Project Directorate Division of Reactor Projects III/IV/V and Special Projects Distribution Copies:

Docket No. 50-320 TMI HQ r/f TMI Site r/f FSchroeder WTravers MMasnik l

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Office: TA/PBTU D/PBTU OJO Beth Concurrees: MMasnik WTravers- 1.Cha r #

Date: 6/ /87 6/ /87 6/ /87 P

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1 DISTRIBUTION

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- Docket File 50-320 NRC PDR Local PDR THI-2 HQ File TMI-2 Site Rdg. File F. Schroeder AD/ Region I W. Travers i M. Masnik OGC/LChandler i S. Lewis D. Hagen E. Jordan J. Partlow T. Barnhart(4)

W. Jones E. Butcher ACRS (10)

GPA/PA ARM /LFMB (w/cy of TAC w/Amdt. No. & date issued) cc: Plant Service List

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