ML20027C398
| ML20027C398 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/14/1982 |
| From: | Wilcove M NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD) |
| To: | Atomic Safety and Licensing Board Panel |
| References | |
| ISSUANCES-OLA, NUDOCS 8210150486 | |
| Download: ML20027C398 (17) | |
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10/14/82 UNITED STATES OF AMERICA NUCLEAR REGULATORY COPEISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of METROPOLITAN EDISON COMPANY, ET AL.
)
Docket No. 50-320 OLA (Three Mile Island Nuclear Station, Unit 2)
)
NRC STAFF NOTICE OF ISSUANCE OF AMENDMENT OF ORDER AND HOTION TO CONFORM PROPOSED TECHNICAL SPECIFICATIONS IN ACCORDANCE HEREWITH The Director, Office of Nuclear Reactor Regulation (Director) has-issued the attached Amendment of Order, dated September 24, 1982, pursuant to his authority under 10 C.F.R. 6 2.717(b). This amendment modifies the license requirements imposed by an Order of the Director dated February 11, 1980, by allowing for separation of the Fuel Handling i
Building Air Cleanup Exhaust System and the Auxiliary Building Air Cleanup i
Exhaust System Technical Specifications. The revised Technical Specifi-cations and Staff's Safety Evaluation Report are also attached.
Pursuant to an Order of the Commission, dated May 12, 1980, this Licensing Board has been designated to conduct the proceeding with respect to the proposed formal license amendment incorporating the j
Technical Specifications proposed in the February 11, 1980 Order.
In
. order to conform the proposed Technical Specifications with the actions taken by the Director in the attached Amendment of Order, the NRC Staff I
hereby moves that the proposed Technical Specifications be formally l
DESIGF TED ORIGINAU ogs g o g sa cer:1riea ny I
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modified to confonn to the Amendment of Order subject to the authority which 10 C.F.R. 5 2.717(b) explicitly preserves in the presiding officer for purposes of this proceeding. Fonnal amendment of the license will, of course, await the outcome of the prospective hearing.
Respectfully submitted,
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Michael N. Wilcove Counsel for NRC Staff Dated at Bethesda, Maryland this 14th day of October 1982 a
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of
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METROPOLITAN EDIS0N COMPANY, ET AL.
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Docket No. 50-320 OLA (Three Mile Island Nuclear Station,
)
Unit 2)
)
CERTIFICATE OF SERVICE I hereby certify that copies of "NRC STAFF NOTICE OF ISSUANCE OF AMENDMENT OF ORDER AND MOTION TO CONFORM PROPOSED TECHNICAL SPECIFICATIONS IN ACCORDANCE HEREWITH" in the above-captioned proceeding have been served on the following by deposit in the United States mail, first class, or, as indicated by an astorisk through deposit in the Nuclear Regulatory Commission's internal mail system, this 14th day of October 1982:
Jofin F. Wolf, Esq., Chairman, Dr. Judith H. Johnsrud Administrative Judge Environmental Coalition on 3409 Shepherd Street Nuclear Power Chevy Chase, MD 20015 433 Orlando Avenue State College, PA 16801 Dr. Oscar H. Paris, Administrative Judge George F. Trowbridge, Esq.
Atomic Safety and Licensing Board Panel Shaw, Pittman, Potts and L
U.S. Nuclear Regulatory Comission Trowbridge l
Washington, D.C.
20555*
1800 M. Street, N.W.
Washington, D.C.
20035 Mr. Frederick J. Shon, Administrative Judge Atomic Safety and Licensing Board l
Atomic Safety and Licensing Board Panel Panel U.S. Nuclear Regulatory Comission U.S. Nuclear Regulatory Comission Washington, D.C.
20555*
Washington, D.C.
20555*
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Karin W. Carter Atomic Safety and Licensing Appeal Assistant Attorney General Panel 505 Executive House U.S. Nuclear Regulatory Comission P. O. Box 2357 Washington, D.C.
20555*
Harrisburg, PA 17120
- Docketing 4 Service Section Mr. William A. Lochstet 0.ffice of the Secretary 119 E. Aaron Drive U.S. Nuclear Regulatory Commission i
State College, PA 16801 Washington,~D.C. 20555 Michael N. Wilcove Counsel for NRC Staff l
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.g Septembar 24, 1982 Docket No. 50-320 i
Mr. B. K. Kanga, Director Three Mile Island Unit 2 GPU Nuclear Corporation P.O. Box 480 Route 441, South Middletown, PA 17057 J
Dear Mr. Kanga:
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The Nuclear Regulatory Commission has issued the enclosed then'dment of Or' der, for the Three Mile Island Nuclear Station, Unit 2.
This Amendment of Order changes the Recovery Mode Proposed Technical Specifications to allow for operations necessary to prepare for future recovery mode activities. The changed requirements had been imposed by the Order of the Director'of the Office of Nuclear Reactor Regulation on February 11, 1980. These changes are being made in response to your requests of April 19,1982 and -
July 7,1982. This Amendment of Order is effective upon issuance.
Copies of the related Safety Evaluation and revised pages for the proposed Technical Specifications and their associated bases are enclosed.
Sincerely, Bernard J. Snyder, Program Director Three Mile Island Program Office Office of Nuclear Reactor Regulation
Enclosures:
- 1. Amendment of Order
- 2. Safety Evaluation
- 3. Proposed Technical Specification Page Changes cc:
J. Barton L. King J. Larson Service List (see attached) l
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, lonald C. Haynes j legional Administrator. Region !
J. 8. Libemen, Esmire J.5. Nuclear Regulatory Commission Deuchin County Office of Emergency Berlack. Israels. Libemen 531 Park Ave.
Prepareeness
<ing of Prussia. PA 19406 Court Mouse. Room 7 25 Sconduey New York, NY 10004 Front & Martet Streets John F. Welf. Esq. Chalmen.
Merristurg PA 17101 Walter W. Cohen Consumer Advocate i Administrative Judge 340g Shepherd Street U.S. Emiremental Protection Agency Desermont of Justice Streweerry Sears.14th P1oor Chevy Chase, a 20015 Region !!! Office Herrisaurg, PA 17127 ATTN: EIS Coordinator Dr. Oscar M. Paris Curtis guilding (Sixth Fleer)
Eduard O. Seert Aesizistrative Judge 4th and Walnut Streets Atomic Safety and Licensing Seerd Penel Philadelphia. PA 19106 Board of Supervisors Londonderry ToimsMp U.S. Nuclear Regulatory Commission RPD #1 Geyers Cacch Road -
Wasnington DC 20555 Thames M. Sarusky Director Middletoun PA 17057 tureau of Radiation Protection I
Mr. Frederick J. Shon Desarment of Emironmental Resources Astert L. Knuse. Esandre' Aministrative Judge P.O. Sea 2063 Atomic Safety aM Licensing Board Penel Merristurg, PA 17120 Assistant Solicitor Knupp and Andrews l
U.S. Nuclear Regulatory Commission P.O. Bom P Washington OC 20055 David Hess Office of Emironmental Planning 407 N. Fn nt Street Karin W. Carter Gesarment of Emironmental Resources Harrisburg. PA 1710B Assistant Attorney General P.O. Sea 2063 505 Esecutive House N - ristury. PA 17120 Robert Q. Pollard Chesapeak Energy Alliance P.O. Box 2357 l
Harrisburg PA,17120 Willis Biaty. Site Manager 50g Montpelier Street U.S. Desertsent of Energy Saltimore. M 21218 l
Dr. Judith M. Jonnsrud P.O. Een 88 l, Emiromental Coalition Middletous. PA 17057-0311 John Levin. Esquire Pennsylvania Public Utilities on Nuclear Power 433 Orlando Avenue Herbert Feinroth, Acting Deputy Comission l
H.O. Rex 3285arrisburg, PA~ l7120 P
Itate College PA 18801 DirectotSf Coordination and Special PmJects. RE 550 Honorette Meet Cohen Georg2 F. Troweridge Esq.
U.S. Dept. of Energy Shaw. Pittmen. Potts aid Washington. DC 20545 512 E-E Mein Capital Sullding Harrisburg, PA 17120 Troweridge 1800 M Street. NW William Lochstet Washington, DC 20036 104 Davey Laboratory Pennsylvante State University Atomic Safety and Licensing University Part. PA 18802 Board Penel U.S. Nuclear Regulatory Comission Randy Myers. Editorial The Patriot Washington DC 20555 812 Market Street Atomic Safety and Licensing Harrisburg, PA 17105 Appeal Penel l
U.S. nuclear Regulatory Commission Robert 8. Iersus Washington. DC 20555 labcock & Wilcos Nuclear Power Generation Division i
Suite 220 Secrstary U.S. Nuclear Regulatory Comission 7910 Wooooont Ave.
ATTN: Chief Bethesda, MD 20B14 l
Docketing & Service Branen dasnington DC 20$55 Judith A. Oorsey 1315 Walnut Street Mr. Larry Hochendoner Suite 1632 Dauphin County Commissioner Philadelpnia. PA 19107 P.O. Som 1295 Harrisburg. PA 17108 1295 Linda W. Little 5000 Hermitage Drive y
N Jonn E. Minnten. Chairperson Raleigh. NC 27612 l
Daupnin County Board of Cosmissioners Dazonin County Courtnouse Marvin !. Louis Front and Martet Streets 6504 5redford Terrsce Harrisourg, PA 17101 Philadelpnia. PA 19149 Jane Lee 183 Valley Road Etters. PA 1731g 1
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s UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION
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In the Matter of
)
Docket No. 50-320 OLA METROPOLITAN EDISON COMPANY, et. al.)
(Three Mile Island Nuclear Station,
)
Unit 2)
AMEN 0 MENT OF ORDER I.
GPU Nuclear Corporation, Metropolitan Edison Company, Jersey Cent Licensee) and Light Company and Pennsylvania Electric Company (collectively, t i
d are the holders of Facility Operating License No. OPR 73, which had a operation of the Three Mile Island Nuclear Station, Unit 2 (TMI-2) a The facility, which is located in levels up to 2772 megawatts thermal.
Londonderry Township, Dauphin County, Pennsylvania, is a pressurized reactor previously used for the commercial generation of electricity.
20, 1979, the Licensee's By Order for Modification of License, dated July ity authority to operate the facility was suspended and the Licensee's auth ling mode was limited to maintenance of the facility in the present shutdown coo l
By further Order of the Director, Office of Nuclear Reacto (44 Fed. Reg. 45271).
t as a new set of formal license requiremen s w 11, 1980, Regulation, dated February s
e the imposed to reflect the post-accident condition of the facility and to as i
continued maintenance of the current safe, stable, long-term cool i
of the facility (45 Fed. Reg.11282).
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Although these requirements were imposed on the licensee by an Order of the Director of Nuclear Reactor Regulation, dated February 11, 1980, the TMI-2 f
license has not been formally amended.
The requirements are reflected in l.!
the proposed Recovery Mode Technical Specifications presently pending before
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the Atomic Safety and Licensing Board.
Hereafter in this Amendment of Order, l
the requirements in question are identified by the applicable proposed Technical 1
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Speci fication.
II.
By letters dated April 19,198?. and July 7,1982, the licensee requested changes 3
to the proposed Technical Specifications, Appendix A for Three Mile Island, Unit 2 (TMI-2). The licensee has requested NRC staff approval for the separation of the Auxiliary Building and Fuel Handling Building Air Cleanup Exhaust System Technical Specifications.
The proposed change would provide separate Technical Specifications for Auxiliary Building and Fuel Handling Building Air Cleanup Exhsust Systems.
Presently section 3.9.12 contains the combined Fuel Handling /
Auxiliary Building Air Cleanup Systems Technical Specification.
The existing l
proposed Technical Specification contained in section 3.9.12 does not accurately reflect the existing design of either the Fuel Handling Building or the Auxiliary Building Air Exhaust System. The staff agrees with the licensee that the changes l
would more clearly define which equipment needs to be operating to provide adequate ventilation capability for the Fuel Handling and Auxiliary Buildings.
The staff has reviewed the design of the Air Exhaust Systems for both the Auxiliary and Fuel Handling Buildings as presented in the licensee's Final Safety Analysis Report (FSAR) and finds that the proposed changes do not The conflict with operational or design characteristics of either system.
changes would require corrective actions within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> if the ventilation
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3-flowrate is not within acceptable limits and suspension of operations involving the movement of liquid and gaseous radwastes in the affected building if the Air It Exhaust System is not returned to an operable condition within four hours.
should also be noted that the changes provide a definition of liquids that would be considered as liquid radioactive waste which would not be moved in the event of loss of the air cleanup system in the building.
This definition is necessary in order not to interfere with required makeup to the reactor coolant system regardless of the status of the Air Exhaust Systems
- The staff finds that the proposed amendment of section 3.9.12 of the proposed Technical Specifications is acceptable.
The staff's safety assessment of this matter is set forth in the concurrently issued Safety Evaluation.
This evaluation concluded, in e
material part, that the modification does not involve a significant hazards consideration and that there is reasonable assurance that the health and safety Prior of the public will not be endangered by operation in the modified manner.
public notice of this Amendment of Order is therefore not required and the action is effective upon issuance.
It was further determined that the modification coes not authorire a change in effluent types or total amounts nor an increase in power level and will i
not result in any significant environmental impact.
In light of this deter-l mination, it was concluded that the instant action is insignificant from the 1
standpoint of environmental impact and, pursuant to 10 CFR 51.5 (d)(4), that l
an environmental impact statement or environmental impact appraisal need not be prepared herewith.
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t' Accordingly, pursuant to the Atomic Energy Act of 1954, as amended, the Director's Order of February 11, 1980, is hereby revised to incorporate the For deletions, additions, and modifications set forth in Attachment A hereto.
further details with respect to this action, see (1) Letter to B. Snyder, I
USNRC, from R. Arnold, Met.Ed/GPU, Technical Specification Change Request
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No. 35 dated April 19, 1982, (2) Amendment to Technical Specification Change Request No. 35, dated July 7,1982, and (3) The Director's Order of i
Februa ry 11, 1980.
l All of the above documents are available for inspection at the Commission's i
Public Document Room,1717 H Street, N.W., Washington, D.C., and at the Commission's Local Public Document Room at the State Library of Pennsylvania, j
Government Publications Section, Education Building, Commonwealth and Walnut Streets, Harrisburg, Pennsylvania 17126.
FOR THE NUCLEAR REGULATORY COMMISSION T L
- ,x Acting Director Edson G. Case, lear Reactor Regulation Office of Nuc f
Effective Date:
September 24, 1982 l
Dated at Bethesda, Maryland 4
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$f SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION GPU NUCLEAR CORPORATION METROPOLITAN EDISON COMPANY
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PENNSYLVANIA ELECTRIC COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY
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i DOCKET NO. 50-320 THREE MILE ISLAND NUCLEAR STATION, UNIT 2 4
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Introduction By letters dated April 19, 1982 and July 7,1982, (References 1 & 2) the licensee requested changes to the preposed Technical Specifications Appendix A, for Three Mile Island, Unit 2 (TMI-2).
The proposed changes would allow for the separation of the auxiliary and Fuel Handling Building Air Cleanup Exhaust Systems proposed Technical Specification (section 3.9.12).
Presently the l
l requirements of proposed Technical Specification section 3.9.12 do not reflect the actual design and operational features of the Auxiliary and Fuel Handling Building Air Cleanup Exhaust Systems and the changes would more clearly define which equipment needs to be operating to provide adequate ventilation capability l
l for the Auxiliary and Fuel Handling Buildings.
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l Summary The licensee has requested NRC staff approval to allow for the separation of the Fuel Handling Building Air Cleanup System and the Auxiliary Building Air Cleanup System Technical Spa.ifications. The proposed changes would accurately reflect the existing air cleanup exhaust systems design and require corrective action if air flow should deviate from the allowable flowrate during normal operation.
In addition to the above, the changes would suspend the movement of liquid and gaseous radioactive wastes if the air cleanup exhaust system in the building is inoperable.
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j Evaluation t
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By Order of the Director, Office of Nuclear Reactor Regulation, dated f
February 11, 1980, a new set of formal license requirements was imposed to reflect the post accident condition of the TMI-2 facility.
The order requi, red i
in section 3.9.12 the Fuel Handling and Auxiliary Building air cleanup systems to be operable with exhaust ventilation flow routed through HEPA filters during j
system operation.
The air exhaust systems for both the Fuel Handling Buf1 ding and Auxiliary i
Building were designed in a manner such that normal flow out of these buildings t
f would bypass the exhaust filters unless airborne contamination levels reached a pre-determined level, then flow would be routed through the air cleanup exhaust filter systems prior to release.
As a result of the March 28, 1979 accident and the February 11, 1980 order, all exhaust air flow from the Fuel Handling and Auxiliary Buildings sust be filtered prior to release to the environment, to minimize the release of airborne contaminants.
The design of the existing air cleanup exhaust system is :uch that redundancy in the system does not exist when flow is routed through the exhaust filter uni ts.
The exhaust filter units for the Fuel Handling and Auxiliary Building air exhaust systems consist of two parallel exhaust filter trains, sized such that each train passes 50% of the required exhaust flow.
Since each filtar train for both the Fuel Handling and Auxiliary air exhaust system is designed for only 50% of the required air exhaust flow,it is possible that a number of anticipated and unanticipated operational occurrences can cause a reduction in the specified I
flow requirement.
To address this design feature the licensee proposed an I
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action statement based on time and air flow. According to the action statement, when any condition arises that reduces air flow, operator actions will be taken to restore the required flow within four hours. However, during such off normal li flow conditions, air flow out of the affected building continues to be filtered l
f and the public health and safety is not compromised.
In the event that corrective actions by the licensee fail to restore the Fuel
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Handling or Auxiliary Building air cleanup exhaust system to operation within the specified time period, all movements of liquid and gaseous radioactive waste'
, in the affected building must be stopped until the inoperable air cleanup exhaust systeg1 is restored to operation.
This requirement is imposed to reduce the possibility of uncontrolled releases of radioactive material into the affected building and the environment.
Since processed water which contains trace quantities of radioactive materials is being reused throughout the plant in a number of rect.very operations, including required makeup to the reactor coolant system, clear criteria are needed to define radioactive liquids.
At the request of the NRC staff, criteria were developed by the licensee and reviewed and approved by the NRC staff to define when liquids should be classified as radioactive.
The criteria are based on not exceeding defined measurable levels of radioactivity.
Reference 2 lists each isotope and its associated mar.imum concentration.
The staff based its approval on measured concentrations in
- enessed water being less than 10 CFR Part 20, Table I concentrations which define the maximum concentration in liquid for a restricted area.
The staff used the above bases because the primary impact of any uncontrolled releases of radioactive material as described above would be on plant personnel.
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.i Environmental Considerations We have determined that the change does not authorize a change in affluent types or total amounts nor an increase in power level and will not result in any significant environmental impact.
Having made this determination, we have
- I ll further concluded that the change involves an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR 51.5 (d)(4),
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4 that an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of this change.
Conclusion Based upon our review of the Auxiliary and Fuel Handling Building Air Ciganup System'(Reference 3) and the change request and amendment to the change request (References 1 & 2), the staff finds that the modification of proposed Technical o
Specification section 3.9.12 is acceptable.
We have also concluded, based on the considerations discussed above, that:
(1) because the change does not involve a significant increase in the probability or consequences of accidents previauslt considered, does not i
involve a significant increase in the possibility of an accident or mal-i function of a different type than evaluated previously and does not involve a significant decrease in a safety margin, it does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the implementation of this change will not be inimical to the common defense and security or to the health and safety of the public.
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i References
- 1) GPU Nuclear letter from R.C. Arnold to B.J. Snyder, Director, TMI Program Office, April 19, 1982,
- 2) GPU Nuclear letter from R.C. Arnold to B.J. Snyder, Director, TMI Program Office, July 7,1982.
- 3) Final Safety Analysis Report, Three Mile Island Nuclear Station-Unit 2, April 4, 1974 h
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,I FACILITY OPERATING LICENSE NO.
DPR-73 DOCKET NO.
50-320 Replace the following pages of Appendir "A" Proposed Technical Specifications i.
with the enclosed pages as indicated.
The revised pages contain vertical lines indicating the area of change.
l Pages I
i 3.9-1 3.9-2 (added)
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..c LIMITING CONDITIONS FOR OPERATION 3.9 RADIOACTIVE WASTE STORAGE FUEL HANDLING BUILDING / AUXILIARY BUILDING AIR CLEANUP SYSTEMS 3.9.12.1 The Fuel Handling Building Air Cleanup Exhaust System shall be OPERABLE with exhaust ventilation flow through the HEPA filters during system operation.
The Fuel Handling Building Air Cleanup Exhaust System is OPERABLE
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when two of the four system air cleanup exhaust fans are OPERABLE.
APPLICABILITY:
At all times.
ACTION:
a.
With the Fuel Handling Building Air Cleanup Exhaust System inoperable due to flow requirements, return the flow to within acceptable limits within four (4) hours or; b.
With the Fuel Handling Building Air Cleanup Exhaust System inoperable (other than as allowed in paragraph 3.9.12.1 a above), suspend all opera-
, tions involving movement of liquid and gaseous radioactive wastes in the
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Fuel Handling Building (other than sarhpling evolutions required by the Technical Specifications or Recovery Operations Plans) until the system l
is restored to OPERABLE status.
3.9.12.2 The Auxiliary Building Air Cleanup Exhaust System shall be OPERABLE l
with exhaust ventilation flow through the HEPA filters during system operation.
The Auxiliary Building Air Cleanup Exhaust System is OPERABLE when two of the four system air cleanup exhaust fans are OPERABLE.
APPLICABILITY:
At all times.
ACTION:
a.
With the Auxiliary Building Air Cleanup Exhaust System inoperable l
due to flow requirements, return the flow to within acceptable limits within four (4) hours or; b.
With the Auxiliary Building Air Cleanup Exhaust System inoperable (other than as allowed in paragraph 3.9.12.2 a above), suspend all operaf 4ns involving movement of liquid and gaseous radioactive wastes in the Auxiliary Building (other than sampling evolutions required by the Technical Specifications or Recovery Operations Plan) until the system is restored to OPERABLE status.
l THREE MILE ISLAND - UNIT 2 3.9-1 September 24, 1982
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i LIMITING CONDITIONS FOR OPERATION
- l EPICOR II PROCESSED WATER 3.9.13 Discharge of water processed by the EPICOR II system shall be pro-l hibited until approved by the NRC.
Water processed by the EPICOR II system lj shall be discharged in accordance with procedures approved pursuant to Specification 6.8.2.
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- l APPLICABILITY
At all times.
!i ACTION:
None except as provided in Specification 3.0.3.
REACTOR BUILDING SUMP WATER 3.9.14 Processing and discharge of water in the Reactor Building sump and Reactor Coolant System shall be prohibited until approved by the NRC.
Water in the Reactor Building sump and Reactor Coolant System shall be processed and discharged in accordance with procedures approved pursuant to Specification
6.8.2. APPLICABILITY
At all times.
ACTION:
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None except as provided in Specification 3.0.3.
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THREE MIL'E ISLAND - UNIT 2 3.9-2 September 24, 1982
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