ML20062K103
| ML20062K103 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 11/06/1980 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | TENNESSEE VALLEY AUTHORITY |
| Shared Package | |
| ML20037B772 | List: |
| References | |
| NUDOCS 8011280229 | |
| Download: ML20062K103 (8) | |
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UNITED STATES OF ANERICA NUCLEAR REGULATORY CCMMISSION In the Matter of
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TEN!4ESSEE VALLEY AUTHCRITY
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Occket No. 50-327 (Sequoyah Nuclear Plant,
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Unit No. 1)
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CRDER FOR MCOIFICATION OF LICENSE I.
The Tennessee Valley Authority (licensee) is the holder of License No. OPR-77, which authcrizes the operation of the Sequoyah Nuclear Plant, Unit No. I at steady j
state reactor core power levels not in excess of 3411 sagawatts thermal (rated peer). The facility consists of a piessurized water reactor located at the licensee's site in Louisa Ccunty, Virginia.
II.
On November 4,1977 the Union of Concerned Scientists (UCS) filed with the Cosmission a " Petition for Emergency and Remedial Relief." The petition sought action in two arias:
fire protection for electrical cables, and e'nvironmental qualification of electrical cosponents. By Memorandum and Order dated April 13, 1978 (7 MRC 400), the Coenission denied certain aspects of the petition and, with respect to other aspects, ordered the NRC staff to take several related actions.
UCS filed a Petition for Reconsideration on May 2,1978. By Memorandum and Order dated May 23, 1980, the Commission reaffirsed its April 13, 1978 decision re9arding the possible. shutdown of operating reactors. However, the Coomission's May 23, 1980 decision directed licensees and the ilRC staff to undertake certain actions.
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. With res::ect to envirorsnental qualification of safety-related electrical equipment, the Comstission determined that the previsions of the two staff documents - the Civ'sfon of Operating Reactors " Guidelines for Evaluating Envirornental Qualification of Class [E Electrical Equipment in Operating Reactors" (DOR Guidelines) and NUREG-0588, ' Interim Staff Position on Envirerssental Qualification of Safety-Related Electrical Equipment," Cecember 1979 (cootes attached) " furs the requirer.:ents which licensees and applicants must meet in order to satisfy those aspects of 10 CFR Part 50, Appendix A General Design Criterion (GTI-4),
which relate to envirormental qualifications of safety-related electrical equi pme nt."
The Commission directed, for replacement parts in operating plants, "unless there are sound reasons to the contrary, the 1974 standard in MUREG-0538 will apply." The Commission also directed the staff to corplete its review of the inforsation sought.fra licensees 1
by Bulletin 79-013 and to complete its review of envirorsnental qualification of safety-related electrical equipment in all cperating plants, including the publication of Safety Evaluation Reports, by February 1,1981. The Commission imposed a deadline that, "by no later than June 30, 1382 all safety-related electrical equisnent in all operating plants shall be qualified to the 00R Guidelines,or NUREG-0588."
1Bulletin 79-018 was not sent to licensees for plants imder reviet as part of the staff's Systematic Evaluation Program. The information sought by Bulletin 79-01B was requested from these licensees by a series of letters and meetings during the months of February and March, 1980.
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The Ccswission recuetted the staff to " keep the Commission and the public apprised of any further findings of incomplete envirereental qualification of safety-related electrical equipment, along with corrective actions taken or planned," and requested the staff to provide bi-senthly progress reports to the Commission.
The Commission further directed that, "In order to leave no room for doubt on this issue, the staff is to prepare additional Technical Seccifications for all operating plants which codify the documentation requirement para-graph of the Guidelines (paragraph 9.0)."
The staff was directed to add these documentation requirements to each license after they were approved by the Commission.
The Ccmmission also pointed out that the various deadlines imposed in its Order, 'do not excuse a licensee from the obligation to mdify or replace inadecuate equipment promptly."
III.
The t.4.ssion has approved the provisions of the license condition set fe-th in Section IV below which specify documentation requirsments and which specifica11y impose on the licensee the requirement of the Commi s-sion's May 23, 1980 Memorandum and Order that by no later than June 30, 1982 all safety-related electrical equipment shall be qualified to the 00R Guide-j it nes or MUREG-0588.
The information developed ering the Commission review of t:w UCS Petition enchasizes the importance of prompt completion of the upgrading of environ-l l
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4-wntal cualification of safety-related electrical ecuipment to conform to the OCR Guidelines or N'SEG-0588 and of adecuate docu rentation of equinnt quali fications. The deadlines set forth in the Commission's Memorandum and Crder dated P.ay 23, 1980, assure that such upgrading will be accocolished In order to assure prompt ccupletion of necessary qua:ificatien prcsiptly.
wert or replacement of unqualified comconents, if necessary, in confor ance with the requirements of the Commission's Memorandu:s and Order dated May 23,1980, such upgrading wort must coseence irmnediately. Therefore, I have concluded that the public health, safety and interest require this Crder for Modification of License to be effective immediately.
IV.
Accordingly, pursuant to the Atomic Energy Act cf 1954, as amended, and the Ceami ssion's Rules and Regulations in 10 CFR Parts 2 and 50, IT IS ORDERED THAT EFFECTIVE DOEDIATELY Facility Cperating License No. DPR-Tl is hereby amended to add the following license condition 2.C.( )(- ) and Appendix A Technical Specification 6.10.2(o):
License Condition 2.C.(,)( ;)
- By no later than June 30, 1982, all safety-related electrical equipment i
in the facility shall be qualtfied in accordance with the provisions of:
Division of Operating Reactors " Guidelines for Evaluatino Envirennental Qualification of Class IE Electrical Equipment in Opersting Reactors" (DCR Guidelines). or, NUREG-0588, ' Interim Staf f Position on Enviremental r
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- 979-289 369 NRCFCRM 318 (916) *4RCM 3:40
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- Cuali fication of Safety-Related Electrical Eouiput," Decerter 1979.
Cocias of these documents are attached to Crder for "odification of License No. DPR-77 dated 'lovember 6,1980.
Accendix A Technical Soecification 6.10.2(o)
" Records for Envirormental Qualification which are covered under the provisions of Paragraph 2.C.(12)(b) cf License No. 7PR-77."
To ef fectuate the foregoing, appropriate pages for incorporation into the Technical Specifications.are attached to this Order.
V.
The licensee or any person whose interest may be affected by this Order nay request a hearing within 20 days of the date of publication of this Order in the Federal Register. Any request for a hearing will net stay the effec-tive date of this Order. Any request for a hearing shall be addressed to the Director, Office of Nuclear Reactor Regulation, U. S. Nuclear Regulatory Commi ssion, Washington, D. C.
20555. A copy of the request should also be sent to the Executive Legal Director, U. S. Nuclear Regulatory Commission, Washington, D. C 20555, and to Herbert 5. Sanger, Jr., Esq., General Counsel, Tennessee Valley Authority, 400 Commerce Avenue, E 11B 33, Knoxville, Tennessee 37902, attorney for the licensee.
I If a hearing is held concerning this Order, the issue to be considered at the hearing shall be:
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1 6-whether all safety-related electrical equipment shculd be qualified as required in Section IV, above, by no later than June 30, 1982.
Operation of the facility on tems ccnststent with this Order is not stayed by the pendency of any proceedings on the Order.
FOR THE NUCLEAR REGlLATORY CPMISSICN Original signed by Darreia. 31se:1:u1 Darrell G. Eisenhut, Director Division of Licensing Office of Wuclear Reactor Regulation Effective Date:
November 6,1980 9ethesda, Maryland Attachments:
1.
License and Technical Specification Pages for this Order 2.
Guidelines for Evaluating Envirormental Qualification of Class IE Electrical Equipment in Ocerating Reactors 3.
NUREG-0588, Interim Staff Position on Envirormental Qualification of Safety-Related Electrical Equipment.
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(9)
Steam Gererator Inspection (Section 5.3.1)
(a) Prior to March 1,1981, TVA shall provide to the NRC the results of its tests to determine the feasibility of using a steam generatc camera device; (b) Prior to start-up after the first refueling, TVA must install inspection ports in each steam generator if the results of the camera device inspection are not satisfactory to the NRC; (c) Prior to start-up after the first refueling, TVA will plug Row 1 of the steam generator tubes, if required by NRC.
(10) Water Chemistry Control Program (Section 5.3.2)
Prior to exceeding five percent power, TVA shall incorporate the following provisiens into the secondary water chemistry control prograr 1.
The Hotwell pump discharge sample point along with continuous cation conductivity mcnitoring will be used as the control point for confirming a condenser leak and for initiating corrective action to locate and repair the leak.
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Impurity-time operating limits for feedwater should be incorporated into the water chemistry program.
The limits use feedwater pH and cation conductivity impurity-time limit values the same as used for steam generator blowdown limits.
(11) Negative Pressure in the Auxiliary Building Secondary Containment Enclosure (ABSCE) (Section o.Z.3)
After the final AESCE configuration is determined, TVA must demonstrate to the satisfaction of the NRC that a negative pressure of 0.25 inches of water gauge can be maintained in the spent fuel storage area and in the ESF pump recm.
(12) Environmental Qualification (Section 7.2.2)
(a) No later than November 1,1980, TVA shall submit information to show compliance with the requirements of NUREG-0588,
" Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment," for safety-related equipment exposed to a harsh environment. Implementation shall be in accordance with NUREG-0588 by June 30, 1982.
(b) By no later than December 1,1980, complete and auditable records must be available and maintained at a central location which describe the environmental qualification method used for all safety-related electrical equipment in sufficient detail to document the degree of compliance with the DCR Guidelines or NUREG-0588. Thereafter, such reccrds should be updated and maintained current as equipment is replaced, further tested, or otherwise further qualified to document complete compliance by June 30, 1982.
ORDER DATED NOVEMBER 6, 1980 i
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= (c) By no later than June 30, 1982, all safety-related electrical equipment in the facility shall be qualified in accordance with the provisions of: Division of Operating Reactors
" Guidelines for Evaluating Environmental Qualification of Class IE Electrical Equipment in Operating Reactors" (DCR Guidelines); or, NUREG-0588, " Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment," December 1979. Copies of these documents are attached to the Order for Modification of License DPR-77 dated November 6,1980 (13) Loss of Non-Class IE Instrumentation and Control Recm System tus vuring uperation taection e.iv>
Prior to exceeding five percent power, TVA must complete revisions to plant emergency procedures to the satisfaction of the NRC.
(14) Engineering Safety Feature (ESF) Reset Centrols (Section 7.11)
In confonnance with IE Bulletin 80-06, TVA shall test the system to identify any further arttas of concern, and TVA shall review the control schemes to deternine that they are the best in terms of equipme:nt control and plant safety.
The results of these test and review efforts shall be prov.ded to the NRC in accordance with the bulletin.
(15) Diesel Generator Reliability (Section 8.3.1)
Prior to operation following the first refueling, TVA shall implement the folicwing design and procedure mcdifications as outlined in Section 8.3.1 of SER Supplement No. 2.
These include: (a) Moisture in Air Starting System; (b) Turbocharger Gear Drive Problem; and, (c) Personnel Training.
(16) Fire Protection System (Section 9.5)
TVA, to the satisfaction of the NRC, shall:
(a) Prior to June 1981, submit the following 3 f tems which deal with the Essential Raw Cooling Water (ERCW) supply: (a) enclose the necessary exposed conduit with 1 1/2-hour fire barrier; (b) reroute train B ERCW pump cables and ERCW transfonner power cables to obtain a minimum 20-fcot separation from train A; and, (c) enclose the ERCW junction box with 1-1/2-hour fire barrier; (b) Prior to November 1,1980,(1) install five fire dampers; and, (2) replace and relocate sprinkler heads in the auxiliary building.
ORCER DATED NOVEftBER 6, 1980