ML19330A853
| ML19330A853 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 07/25/1980 |
| From: | Parris H TENNESSEE VALLEY AUTHORITY |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0694, RTR-NUREG-694 NUDOCS 8007290651 | |
| Download: ML19330A853 (6) | |
Text
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500A Chestnut Street Tower II July 25, 1980 Mr. H. R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Denten:
In the Matter of the Application of
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Docket No. 50-327 Tennessec Valley Authority
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TVA has evaluated the design and equipment delivery schedules for the modifications at Sequoyah Nuclear Plant required as dated items in NUREG-0694, "TMI Requirements for New Operating Licenses." As a result of this evaluation, three items have been identified as not meeting the January 1, 1981, implementation. Another item has been identified as meeting the implementation date, but installation would be deferred to coordinate work schedules. An evaluation of each individual item is included as an enclosure.
Based on present schedule projections, it appears that all equipment for work requiring a plant outage would be available during the March -
June time frame.
If required, TVA could perform those work items at that time. However, TVA fully believes that the proper time to perform work of this nature and scope-is the first refueling outage.
The first refueling outage is presently scheduled for early 1982.
Very truly yours, TENNESSEE VALLEY AUTHORITY f
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G. Parris Manager of Power Enclosure g007290bh
SEQUOYAH NUCLEAR PLANT UNIT 1 COMPLlANCE WITH DATED ITEMS IN PART 4 0F NUREG-0694 I.A.l.1 Shift Technical Advisor The requirements for Shift Technical Advisor will be met by January 1, 1981.
I.A.2.1 1mmediate Upgrading of Operator and Senior Operator Training and Qualification The requirements for upgrading training and qualification have been met.
I.A.2.3 Administration of Training Programs for Licensed Operators The requirements for training programs have been met.
I.A.3.1 Revised Scope and Criteria for Licensing Examinations The requirements for licensing examinations have been met.
I.C.1 Short-Term Accident Analysis and Procedure Revision All analyses and procedure guidelines are being developed with other utilities through the Westinghouse Owners Group. As reported in NUREG-0694, NRC has not fully defined the scope of this item.
II.B.1 Reactor Coolant System Vents TVA believes the RCS vent system can be installed by January 1, 1981.
Drawings are scheduled for delivery to the site during early October.
The pacing material problems are the Target Rock solenoid valves.
Slippage in either of these areas will result in an installation delay.
This modification involves a considerable amount of work in routing wiring and conduit.
It would require approximately two months in the cold shutdown mode to install.
Based on involvement with the Westinghouse Owners Group, it is TVA's understanding that this system must be used with the vessel level instrument.
This is the primary reason for delaying this item.
ENCLOSURE l
SEQUOYAH NUCLEAR PLAbiT UNIT 1 COMPLIANCE WITH DATED ITEMS IN PART 4 of NUREG-0694
SUMMARY
NUREG-0694 lists 15 dated items for compliance by a new operating license plant. The following is a brief summary of TVA's compliance with these requirements for the Seq 2oyah Nuclear Plant.
TVA is presently in compliance with eight items.
TVA could meet the schedule for three items with very little or no uncertainty.- However, one item will be rescheduled to minimize outage time.
TVA will not meet the schedule for three items because of design, procurement, or installation problems.
One item is not applicable to Sequoyah.
It is important to discuss at this time some of the background and bases for this report.
The projected schedules for those items that do not meet the schedule dates listed in NUREG-0694 are based on promised delivery dates for drawings and materials and projected installation man-hours estimated from preliminary scoping documeats.
Experience has shown that this type of scheduling tends to be optimistic.
Unanticipated design changes and procurement. problems'do occur.
Based on present schedule projections, TVA believes that the equipment would become available during the period betwe2n January and June 1981.
TVA could schedule the modifications during this time, as determined by actual material deliveries. However, because of the nature and scope of the modifications, TVA fully believes that it is most appro-priate to schedule this type of work during the first refueling outage.
A discussion lof each individual item is provided on the following pages.
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II.B.2 Plant Shielding The requirements for plant shielding have been met.
If TVA is unable to install the post-accident sampling system and has to provide a temporary system, plant shielding requirements for the temporary system may have to be installed. These shielding requirements will be con-sidered as part of the post-accident sampling system.
II.B.3 Post-Accident Sampling TVA believes the post-accident sampling system can be completed between August and November 1981. The drawings and basic equipment delivery are expected in November 1980.
However, the critical component is the cooling water booster pump. This item cannot be devlivered before June 1981, and may be as late as October 1981.
This modification would require approximately three months to install with six weeks in the cold shutdown mode.
II.D.1 Relief and Safety Valve Test Requirements TVA is participating in the EPRI program.
The expected completion date is July 1, 1981.
II.E.1.2 Auxiliary Feedwater Initiation and Indication TVA's des?gn meets the intent of the requirement as stated in TVA's response to NUREG-0578.
II.E.4.1 Containment Dedicated Penetration This requirement does not apply to Sequoyah.
II.F.1 Additional Accident Monitoring Instrumentation i
a.
Containment Pressure Monitor - TVA has an extended range containment pressure monitor installed which meets IEEE 323-1971 requirements.
An extended range containment pressure monitor which meets IEEE 323-1974 requirements will be installed at the first outage of sufficient duration after such an instrument has been procured.
At this time, there.are no extended range pressure monitors available which meet the IEEE 323-1774 requirements.
Instal-lation of new monitors would require a plant outage of one week or less.
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b.
Containment Water Level - TVA has met the requirements for contain-i ment water level monitors.
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Containment Atmosphere Hydrogen Concentration Monitor - TVA has met the requirements for a containment hydrogen concentration monitor.
l d.
High-Range Containment. Radiation Monitor - TVA has recently ordered high-range radiation monitors lfor installation inside the containment building. TVA is hopeful that the radiation moni-tors could be delivered by March 1981.
Installation of these i
. monitors requires approximately three weeks in the cold shutdown mode.
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Effluent Monitors --This modification requires a significant amount e.
of work in routing of wiring and conduit. Because of this fact, TVA plans to maintain a flexible installation schedule in conjunction
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with other modifications involving similar work.
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Material delivery for this modification is expected about January 1, 1981, and modifications will take approximately one month to complete.
i TVA meets the requirement to provide the capability to continuously l
sample and perform onsite analysis of the radionuclide and particulate
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samples.
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l II.F.2 Inadequate Core Cooling Instruments TVA believes that the reactor coolant vessel level instrument is the critical path-item during an outage to install the outage-dependent modifications..The vessel level instrument could be installed by May 1, j
1981, if present-delivery schedules ~for drawings and materials are met.
Westinghouse drawings and materials are ' promised for delivery by j'
November 1980. Approximately two months of TVA engineering work are fi't?lved af ter delivery of.the Westinghouse drawings.
This work involves j-the location and wiring layouts for the peripheral equipment (e.g., tem-perature compensation equipment cabinets).
This modification involves a considerable amount of work in routing I
wiring and. conduit.
It would. require approximately two months in cold shutdown mode to install.
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' Based on involvement with the Westinghouse Owners Group, TVA believes
- that. the deJivery schedule for drawings and materials for this system
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have the largest uncertalaty associated with them, i
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III.A.1.2 Upgrade Emergency Support Facilities TVA has completed the conceptual design of the onsite Technical Support Center (TSC) and expects to complete the modifications on a schedule consistent with draft NUREG-0696.
The centralized Emergency Operations Facilities (EOF) cannot be upgraded until the onsite TSC is upgraded.
Therefore, the EOF will be upgraded on a schedule consistent with that for completion of the onsite TSC.
III.D.3.3 Inplant Radiation Monitoring The requirements for inplant radiation monitoring have been met.
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