ML19257B289
| ML19257B289 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 01/07/1980 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8001150502 | |
| Download: ML19257B289 (6) | |
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TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 37401 400 Chestnut Street Tower II January 7, 1930 Mr. James O'Reilly, Director Office of In pection and Enforcement U.S. Nuclear egulatory Commission Region II - Su te 3100 101 Marietta St eet Atlanta, Georg 30303
Dear Air. O'Reilly:
SEQUOYAli NUCLEAR PLANT UNIT 1 - REVIEW OF PLANT STATUS AUD PREPARATI0h5 FOR OPERATING LICENSC ISSUALCE In accordance with R. C. Lewis' letter dated February 21, 1979, RII RhV 50-327/79-7, Tennessee Valley Authority (TVA) hereby transmits a listing of significant outstanding items that are required for plant operation which may not be complete until after unit 1 fuel loading.
IVA's review of the Sequoyah Nuclear Plant Final Safety Analysis Report (FSAR) cammitments has identified a small nu=ber of significant or safety-related items that may not be completed before fuel loading. TVA has s
evaluated these iteds and determined that the incomplete status of these items at the time of fuel loading and/or during the interim low power special test series will have no adverse effect on the health and safety of the general public or TVA employees.
Enclosures 1 and 2 identify those items which are expected to be completed after fuel loading and after initial criticality, respectively. The lists include TVA's evaluation of their impact on facility activities subsequent to issuance of the Operating License. TVA, therefore, requests that the Operating License for Sequoyah unit 1 be conditioned to reflect the com-plation of the items identified in the enclosures.
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. fir. James P. O'Reilly, Director January 7, 1980 If you have any questions concerning this matter, please get in touch with D. L. Lambert at FTS 854-2581.
Very truly yours, TENNESSEE VALLEY NUTuGRITY L. M.111118, !!anager Nuclear Regulation and Safety Enclosures Mr. Victor Stallo, Jr., Director (Enclosures), /
V cc:
Office of Inspection and Enforcement U.S. Nuclear Regulatory Cot: mission Washington, DC 20555 1749 104
ENCLOSURE 1 SEQUOYAH NUCLEAR PLANT UNIT 1 SIGNIFICANT WORK ITEMS THAT WILL BE INC0!iPLETE AT FUEL LOADING 1.
Volume Control Tank Room Fire Door (ECN-2537) - Adequate ven611ation in this room cannot be provided with the "A" label fire door presently installed.
A "B" label door with a louver will be provided. To provide adequate ventilation until the new door is installed, the "A" label door door will be propped open. Propping open the "A" label door violates our commitment to compartmentalization for fire protection. A fire watch will be provided until the "B" label door is installed.
Justification With adequate room ventilation and the fire watch, protection against hydrogen accumulation and compliance with our compartmentalization com-mitment is ensured.
2.
Steam Generator and Pressurizer Level Instrumentation Reference Leg Insulation (IE Bulletin 79-21) - Insulation of the reference leg of the level instru-mentation from a main steamline or feedwater break accident environment may not be complete before fuel loading.
Insulation will be installed before initial criticality.
Justification The trip function and the level instrumentation for accident mitigation and control will not be required until the reactor goes critical.
3.
Barton Steam Flow Transmitters - The allowable span of Lot 2 Barton transmitters has been modified by Barton to account for elevation differences between the instrument taps and the instruments themselves.
Installation of the modified transmitters may not be accomplished by fuel loading.
Foxboro transmitters will be used until the modified Lot 2 Barton transmitters can be installed before 1 percent power.
Justification The trip function of the transmitters will not be needed until 1 percent power.
4.
Defective Charcoal Adsorber Trays (NCR 17P) - Awaiting replacement of trays and subsequent NRC-0IE review.
Justification There is no adverse effect on the health and safety of the general publid or plant employees if incomplete at time of fuel loading.
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5.
Control Rod Drop Events Yield Low DNBR (NCR NEB 79-6) - Interim report was sent justifying low power operation. Westinghouse will supply input for final report before full power operation.
Justification There is no adverse effect on the health and safety of the general public or plant employees if incomplete at time of fuel loading.
6.
Excessive Output Fluctuations of Foxboro Instruments (NCR SWP 79-S-5) -
An interim report was sent justifying unit 1 operation with interim modifications. Awaiting replacement of voltage inverters and NRC-01E review.
Justification There is no adverse effect on the health and safety of the general public or plant employees if incomplete at time of fuel loading.
7.
Damaged Tubes in Containment Spray Heat Exchangers (NCR 16P) - Awaiting final report. Modifications and testing of the CS and CCW heat exchangers will be needed before entry into Mode 4.
Justification There is no adverse effect on the health and safety of the general public or plant employees if incomplete at time of fuel loading.
8.
Undetectable Failure in SSPS P-4 Signal (NCR NEB 79-4) - Final report was sent to NRC-0IE on December 20, 1979.
TVA must revise procedures to incor-porate testing of the P-4 contacts before entry into Mode 4.
Justification There is no adverse effect on the health and safety of the general public or plant employees if incomplete at time of fuel loading.
9.
Installation of Coils in AFW and EGTS Systems (NCR 7P) - Awaiting completion of work plans 3269 and 3270 and subsequent review by NRC-0IE.
Justification There is no adverse effect on the health and safety of the general public or plant employees if incomplete at time of fuel loading.
10.
Pressurizer Relief Line Repair (NCR SWP 79-S-8) - Awaiting results of NRC site visit January 16, 1980.
Justification There is no adverse effect on the health and safety of the general public or plant employees if incomplete at time of fuel loading.
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11.
Auxiliary Building Ventilation System Damper Actuators (NCR 19P) - Awaiting completion of modification of all Bettis robot-arm valve actuators which are installed sideways or upside down to prevent key f rom falling out.
I Justification There is no adverse effect on the health and safety of the general public I
or plant employees if incomplete at time of fuel loading.
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ENCLOSURE 2 SEQUOYAH NUCLEAR PLANT UNIT 1 SIGNIFICANT WORK ITEMS THAT WILL BE INCOMPLETE AT INITIAL CRITICALITY 1.
Flamemastic Coating of Cables (ECN-2462) - We are committed to have electrical cables at points where A and B train cables interact coated with Flamemastic w'1 thin five feet of the interaction.
Final cable pulling resulted in routing new cables through interaction points that have already been coated. We will stop pulling and coat new cable at any interaction point when the number of uncoated cables reaches 10 per interaction point.
Justification The amount of insulation involved with 10 conductors does not create a significant hazard. This position has been previously approved at the Browns Ferry Nuclear Plant.
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