ML20129G955

Forwards Amend 51 to License DPR-73 & Safety Evaluation. Amend Revises TS to Extend Surveillance Interval for Demonstrating Operability of Containment Airlock

ML20129G955
Person / Time
Site:	Three Mile Island
Issue date:	10/24/1996
From:	Thonus L NRC (Affiliation Not Assigned)
To:	James Knubel GENERAL PUBLIC UTILITIES CORP.
Shared Package
ML20129G958	List: ML20129G955 ML20134D776 ML20134D781
References
TAC-M91710, NUDOCS 9610300281
Download: ML20129G955 (3)

Text

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c Mr. James Knubel, Vice President October 24, 1996 and Director - TMI GPU Nuclear, Inc.,

i Post Office Box 480 Middletown, PA 17057  ;

SUBJECT:

ISSUANCE OF AMENDMENT NO. 51 FOR THREE MILE ISLAND NUCLEAR STATION, UNIT N0. 2 (TAC NO. M91710) l

Dear Mr. Knubel:

The Commission has issued the enclosed Amendment No. 51 to Possession-Only License No. DPR-73 for Three Mile Island Nuclear Station, Unit No. 2. The

amendment consists of changes to the Technical Specifications (TS) in response to your application dated February 16, 1995.

The amendment revises the Technical Specifications (TS) to extend the surveillance interval for demonstrating operability of the containment airlock. It also revises the general surveillance requirements to allow a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period to perform an inadvertently missed surveillance consistent with the Revised Standard Technical Specifications for Babcock and Wilcox Plants.

A copy of the related Safety Evaluation is also enclosed. A notice of issuance will be included in the Commission biweekly Federal Reaister notice.

Sincerely, Original signed by:

Lee H. Thonus, Project Manager Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation l

Docket No. 50-320 I

Enclosures:

1. Amendment No. 51 to DPR-73

2. Safety Evaluation cc w/ enclosures:

0-'/ l See next page DISTRIBUTION:

Docket File 50-320 PUBLIC PDND r/f TMartin BGrimes SWeiss EHylton LThonus OGC (015-B-18) GHill (2) (T5-C3) CGrimes (013-H-15) Region I SBajwa '

PDND:P PD PDND:SC [ OGC D LThonu E on SBajwa E 'MM CU SWeiss I (0/S7/96 /J$/96 /d /g/96 (o /0 /96 /C/y4/96 ]

0FFICIAL RECORD COPY DOCUMENT NAME: G:\SECY\THONUS\ AMEND 51 961bbo~281961024 PDR ADOCK 05000320 g fR.E CENTS #

P PDR ,

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NUCLEAR REGULATORY COMMISSION o WASHINGTON, D.C. 2066dL4001 s.,*****/ October 24, 1996 Mr. James Knubel, Vice President and Director - TMI GPU Nuclear, Inc.

Post Office Box 480 Middletown, PA 17057

SUBJECT:

ISSUANCE OF AMENDMENT N0. 51 FOR THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 2 (TAC NO. M91710)

Dear Mr. Knubel:

The Commission has issued the enclosed Amendment No. 51 to Possession-Only License No. DPR-73 for Three Mile Island Nuclear Station, Unit No. 2. The amendment consists of changes to the Technical Specifications (TS) in response to your application dated February 16, 1995.

The amendment revises the Technical Specifications (TS) to extend the surveillance interval for demonstrating operability of the containment airlock. It also revises the general surveillance requirements to allow a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period to perform an inadvertently missed surveillance consistent with the Revised Standard Technical Specifications for Babcock and Wilcox Plants.

A copy of the related Safety Evaluation is also enclosed. A notice of  !

issuance will be included in the Commission biweekly Federal Reaister notice, l l

Sincerely, f Of Lee H. Thonus, Project Manager Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No. 50-320

Enclosures:

1. Amendment No. 51 to DPR-73

2. Safety Evaluation cc w/ enclosures:

See next page I

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.s J. Knubel Three Mile Island Nuclear Station GPU Nuclear, Inc. Unit No. 2 Docket No. 50-320 cc:

Regional Administrator, Region I Mr. David J. McGoff U.S. Nuclear Regulatory Commission Office of LWR Safety and Technology 475 Allendale Road NE-23 King of Prussia, Pennsylvania 19406 U.S. Department of Energy Washington, D.C. 20545 Dr. Judith H. Johnsrud Environmental Coalition on Nuclear Mr. Wythe Keever Power The Patriot 433 Orlando Avenue 812 Market Street State College, Pennsylvania 16801 Harrisburg, Pennsylvania 17105 Ernest L. Blake, Jr., Esq. Mr. Robert 8. Borsum Shaw, Pittman, Potts, and Trowbridge B & W Nuclear Technologies 2300 N Street, N.W. Suite 525 Washington, D.C. 20037 1700 Rockville Pike  ;

Rockville, Maryland 20852 Secretary U.S. Nuclear Regulatory Commission Ms. Jane Lee Washington, D.C. 20555 183 Valley Road Etters, Pennsylvania 17319 Mr. Russell Schaeffer, Chairperson Dauphin County Board of Commissioners Mr. Walter W. Cohen, Consumer Dauphin County Courthouse Advocate  !

Front and Market Streets Department of Justice i Harrisburg, Pennsylvania 17120 Strawbsrry Square,14th Floor l Harrisourg, Pennsylvania 17127 Mr. William P. Dornsife, Director Bureau of Radiation Protection U.S. Environmental Prot. Agency Department of Environmental Protection Region III Office  !

13th Floor, Rachel Carson State Office ATTN: EIS Coordinator Building 841 Chestnut Street P. O. Box 8469 Philadelphia, Pennsylvania 19107 Harrisburg, Pennsylvania 17105-8469 Mr. 8. A. Mehler Mr. Ad Crable GPU Nuclear, Inc.

Lancaster New Era P. O. Box 480 8 West King Street Middletown, Pennsylvania 17057 Lancaster, Pennsylvania 17601 Ms. Michele G. Evans l Senior Resident Inspector (TMI-1) l U.S. Nuclear Regulatory Commission P. O. Box 311 Middletown, Pennsylvania 17057  !

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p uru y & UNITED STATES j

j NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 2006Hm01 4

9 . . . . . ,8 GPU NUCLEAR. INC DOCKET NO. 50-320 THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 2 AMENDMENT TO POSSESSION-0NLY LICENSE Amendment No. 51 License No. DPR-73

1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment filed by GPU Nuclear Corporation (GPUN or licensee) dated February 16, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Commisr, ion's rules and regulations as set forth in 10 CFR Chapter I; B. The facility will be maintained in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the regulations of the Commission; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the regulations of the Commission and all applicable requirements have been satisfied.

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2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(1) of possession-Only No. DPR-73 is hereby amended to read as follows:

(1) Technical Specifications The Technical Specifications, as revised through Amendment No. 51, are hereby incorporated into this license. The licensee shall maintain the facility in accordance with the Technical Specifications and all Commission Orders issued subsequent to the date of the possession only license.

3. This license amendment is effective as of the date of issuance.

! FOR THE NUCLEAR REGULATO COMMISSION

c f Seymour H. Weiss, Direct Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management 4

Office of Nuclear Reactor Regulation l

Attachment:

Changes to the Technical Specifications l Date of Issuance: October 24, 1996 i

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ATTACHMENT TO LICENSE AMENDMENT NO. 51 POSSESSION-0NLY LICENSE NO. DPR-73 DOCKET N0. 50-320 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

REMOVE INSERT

3/4.0-1 3/4.0-1 4 3/4.1-4 3/4.1-4 i i B3/4.0-1 83/4.0-1 83/4.0-2 B3/4.0-2 i

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3/4.0 LIMITING CONDITIONS FOR PDMS AND SVRVEILLANCE RE0VIREMENTS 3/4.0 APPLICABILITY LIMITING CONDITIONS FOR PDMS 3.0.1 Limiting Conditions for PDMS and ACTION requirements shall be applicable during POST-DEFUELING MONITORED STORAGE or other conditions '

specified for each specification.

3.0.2 Adherence to the requirements of the Limiting Condition for PDMS and/or associated ACTION within the specified time interval shall constitute compliance with the specification. In the event the Limiting Condition for  !

PDMS is restored prior to expiration of the specified time interval, completion of the ACTION statement is not required.

3.0.3 In the event a Limiting Condition for PDMS and/or associated ACTION requirements cannot be satisfied because of circumstances in excess of those l addressed in the specification, initiate appropriate actions to rectify the problem to the extent possible under the circumstances and submit a report to the Commission pursuant to the requirements of 10 CFR 50.73.

SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during PDMS or other conditions i specified for individual Limiting Conditions for PDMS unless otherwise stated in an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval.

4.0.3 Failure to perform a Surveillance Requirement within the specified time interval shall constitute-a failure to meet the OPERABILITY requirements for a Limiting Condition for PDMS. Exceptions to these requirements are stated in the individual Specifications. Surveillance Requirements do not have to be performed on inoperable equipment. I 4.0.4 If it is discovered that a surveillance was not performed within its i specified frequency, then compliance with the requirement to declare the LC0 not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to i the limit of the specified frequency, whichever is less. This delay period is i permitted to allow performance of the Surveillance.

l Three Mile Island-Unit 2 3/4.0-1 Amendment 51

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l CONTAINMENT AIR LOCKS LIMITING CONDITIONS FOR PDMS i 3.1.1.3 Each Containment Air Lock shall be OPERABLE with at least one door  ;

closed except when the air lock is being used for transit entry and exit in accordance with site-approved procedures.

APPLICABILITY: PDMS ACTION:

With no Containment Air Lock door OPERABLE, restore at least one door to 3 OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE RE0VIREMENTS l 4.1.1.3 Each Containment Air Lock shall be demonstrated OPERABLE annually by performing a mechanical operability check of each Air Lock Door, including a visual inspection of the components and lubrication if necessary and by visually inspecting the door seals for significant degradation. When both Containment Air Lock doors are opened simultaneously, verify the following  !

conditions: l

a. The capability exists to expeditiously close at least one Air Lock door;

b. The Air Lock doors and Containment Purge are configured to restrict the ,

outflow of air in accordance with site-approved procedures; and

c. The Air Lock doors are cycled to ensure mechanical operability within I seven days prior to opening both doors.  !

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l Three Mile Island - Unit 2 3/4.1-4 Amendment 51  !

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I 3/4.0 APPLICABILITY BASES The specifiestions of this section provide the general requirements applicable to each of the Limiting Conditions for PDMS and Surveillance Requirements within Section 3/4.

3.0.1 This specification defines the applicability of each specification in terms of PDMS or other specified conditions and is provided to delineate t

specifically when each specification is applicable.

3.0.2 This specification defines those conditions necessary to constitute compliance with the terms of an individual Limiting Condition for PDMS and associated ACTION requirement.

3.0.3 The specification defines the action and reporting requirements for those circumstances where the ACTION statement for Limiting Conditions for >

PDMS was exceeded.  :

4.0.1 This specification provides that surveillance activities necessary to ensure the Limiting Conditions for PDMS are met and will be performed during the condition for which the Limiting Conditions for PDMS are applicable.

4.0.2 The provisions of this specification provide allowable tolerances for performing surveillance activities beyond those specified in the nominal  :

surveillance interval. These tolerances are necessary to provide ' operational flexibility because of scheduling and performance considerations. The phrase "at least" associated with a surveillance frequency does not negate this )

allowable tolerance value and permits the performance of more frequent surveillance activities. It is not intended that this provision be used ,

repeatedly as a convenience-to extend surveillance intervals beyond that j specified. The allowable tolerance is based on engineering judgement and the I recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirements. This provision is sufficient to ensure that the reliability i ensured through surveillance activities is not significantly degraded beyond  !

that obtained from the specified surveillance interval.  !

4.0.3 The provisions of this specification set forth the criteria for i determination of compliance with the OPERABILITY requirements of the Limiting l Conditions for PDMS. Under this criteria, equipment, systems or components i are assumed to be OPERABLE if the associated surveillance activities have been satisfactorily performed within the specified time interval. Nothing in this provision is to be construed as defining equipment, systems or components OPERABLE, when such items are found or known to be inoperable although still meeting the Surveillance Requirements.

Three Mile Island - Unit 2 83/4.0-1 Amendment 51

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3/4.0 APPLICABILITY (Con't) 1

BASES 4.0.4 This specification establishes the flexibility to defer declaring affected equipment inoperable or an affected variable outside the specified 3

limits when a surveillance has not been completed within the specified'

frequency. A delay period of up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> applies from the point in time  ;

i that it is discovered that the required surveillance has not been performed  :

l and not at the time that the specified frequency was not met.

} The delay period provides an adequate time to complete surveillances that have 2 been missed. This delay period permits the completion of a surveillance

! before complying with required actions or other remedial measures that might '

preclude completion of the surveillance.

l- The basis for this delay period includes consideration of unit conditions,

! adequate planning, availability of personnel, the time required to perform the

surveillance, the safety significance of the delay in completing the required

!- surveillance, and the recognition that the most probable result of any j particular surveillance being performed is the verification of conformance

, with the requirements.

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When a surveillance with a frequency based not on time intervals, but upon specified unit conditions or operational situations, is discovered not to have i been performed when specified, this provision allows the full delay period of l

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to perform the surveillance.

J Failure to comply with specified surveillance frequencies is expected to be an i infrequent occurrence. Use of the delay period is not intended to be used as j an operational convenience to extend surveillance intervals.

If a surveillance is not completed within the allowed delay period, then the

, equipment is considered inoperable or the variable is considered outside the specified limits and the completion times of the required actions for the

! applicable LCO conditions begin immediately upon expiration of the delay i period. If a surveillance is failed within the delay period, then the

! equipment is inoperable, or the variable is outside the specified limits and the completion times of the required actions for the applicable LCO conditions begin immediately upon failure of the surveillance.

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! Completion of the surveillance with the delay period allowed by this l specification, or within the completion time of the actions, restores

compliance.

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4 I Three Mile Island - Unit 2 83/4.0-2 Amendment 51 i

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l utn e t UNITED STATES j

• j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666 4 001 l

\ *****/ l SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION 1

RELATED TO AMENDMENT N0. 51 TO POSSESSION-0NLY LICENSE NO. DPR-73 i GPU NUCLEAR. INC l THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 2 DOCKET NO. 50-320 l

1.0 INTRODUCTION

l By letter dated February 16, 1995, GPU Nuclear, Inc. then knon as GPU Nuclear Corporation, (GPUN, or licensee) submitted a request for changes to the Technical Specifications (TS) for Three Mile Island Nuclear Station, Unit No. 2. The proposed changes would extend the surveillance interval to demonstrate operability of the containment airlocks from quarterly to  ;

annually. The purpose of the change is to decrease the personnel exposure associated with implementing the . 'veillance. The changes would also allow a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to correct any inadvertently missed surveillance and delete j an administrative requirement regarding time extensions on consecutive '

surveillance; these proposed changes would make the THI-2 Technical l Specifications consistent with TMI-l and the Standard Technical Specifications I for Babcock and Wilcox Plants (NUREG-1430, September 1992). )

20 BACKGROUND Three Mile Island Unit 2 (THI-2) is in a permanently shutdown and defueled ,

state of post-defueling monitored storage (PDMS), which is similar to SAFSTOR.  !

The remaining THI-2 staff conducts periodic monitoring and surveillance and limited dismantlement activities. Since the THI-2 accident on March 28, 1979, the licensee has conducted a comprehensive cleanup program to ensure that the facility is safe and stable. Following mitigation of the accident :nd stabilization of the facility, the major efforts of the licensee during the past 17 years have included partial facility decontamination; removal of fuel from the reactor vessel and other facilities; offsite shipment of substantial quantities of both high-level and low-level radioactive wastes; and the removal, treatment, and disposal of the accident-generated water. The NRC staff issued a license amendment with attached safety evaluation on December 28, 1993, which allowed the facility to enter this long-term storage mode. The licensee is maintaining the facility in long-term storage until Three Mile Island Nuclear Station, Unit No. 1 (THI-1), located on the same site as TMI-2, permanently ceases operation, at which time both facilities will be decommissioned. '

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3.0 EVALUATION l

The proposed amendment would revise specification 4.1.1.3 of the surveillance 4 section of the technical specifications (TS). This section currently requires l that the airlock surveillance be performed quarterly. Allowing an annual surveillance would make the containment airlock surveillance consistent with ,

the remainder of the containment penetrations and save 50 person-millirem per i surveillance. )

The NRC staff reviewed the licensing basis for the containment integrity l surveillance and could not identify any adverse safety impact resulting from '

this change. The staff's previous safety evaluation for PDMS conditions,  !

dated December 28, 1993, considered a variety of accident scenarios including (1) vacuum canister failure, (2) high pressure spray of contamination, (3) cutting contaminated pipe, (4) break of contaminated pipe, (5) elevator / stairwell fire in containment, (6) fire in the containment D-rings, (7) containment penetration failure, and (8) the rupture and release i of resins from Makeup and Purification Demineralizers. For the most severe of these accidents, the fire in the containment D-rings, the total body and bone l dose to the maximally exposed individual at the site boundary was 49 and 51 mrem, respectively. These results are 6 small part of the 10 CFR Part 20 limits and a very small fraction of 10 CFR Part 100 limits. The proposed change would not alter the staff's previous analysis and would not create a new potential accident scenario. The proposed change is acceptable to the NRC staff.

The proposed amendment would also revise TS Section 4.0.2 regarding the allowable time extension to complete surveillance requirements. The current specification allows a 25 percent time extension on each surveillance and a total 25 percent time extension on a series of four consecutive surveillances.

The proposed change deletes the limitation regarding four consecutive surveillances. This proposed change will not affect plant equipment or safety. The change will make the THI-2 TS consistent with the Standard Technical Specifications for Babcock and Wilcox Plants (NUREG-1430) and with the TMI-l TS. The bases for the TS, which are included with Appendix A to the facility license but are not considered part of the TS, will be revised to reflect the change in 4.0.2. The staff finds this change acceptable.

The proposed change would modify TS Section 4.0.4 to allow a 24-hour period to ,

complete a missed surveillance without entering an action statement. This '

delay is permitted to allow performance of the surveillance. This change will not affect plant equipment or safety. The change will make the TMI-2 TS l consistent with the Standard Technical Specifications for Babcock and Wilcox '

Plants (NUREG-1430, September 1992) and with the THI-1 TS. The bases for the TS, which are included with Appendix A to the facility license but are not considered part of the TS, will be revised to reflect the change in 4.0.4. l The staff finds this change acceptable.

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4.0 STATE CONSULTATION

l In accordance with the regulations of the Commission, the Pennsylvania State official was notified of the proposed issuance of the amendment. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendment changes surveillance requirements. The NRC 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 i occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards )

4 consideration, and there has been no public comment on such finding ,

(61 FR 28616). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(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 the amendment. 1 1

6.0 CONCLUSION

l The Commission has concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the i public will not be endangered by operation in the proposed manner, (2) such 1 activities will be conducted in compliance with the regulations of the Commission, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: Lee H. Thonus Date: October 24, 1996 1