ML19347C724

Proposed Changes to Tech Specs,Deleting Inappropriate Items from License & Moving Completion Date of Items Originally Scheduled 820101 to End of First Refueling Outage Scheduled for Aug 1982

ML19347C724
Person / Time
Site:	Sequoyah
Issue date:	12/30/1980
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML19347C723	List: ML19347C722 ML19347C724
References
NUDOCS 8101050227
Download: ML19347C724 (3)

Text

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LJ ENCLOSURE PROPOSED CHANGES TO SEQUOYAH NUCLEAR PLANT UNIT 1 OPERATING LICENSE DPR-77 8101oao##7

PROPOSED CHAN0ES TO SEQUOYAH NUCLEAR PLANT UNIT 1 OPERATING LICENSE DPR-77

1. License condition 2.c. (10), Water Chemistry Control Program This requirement can be deleted from the operating license. The secondary water chemistry control program is in force at Sequoyah unit

1. The provisions noted in the license condition have been incor-porated into the Sequoyah program. TVA is required to maintain the chemistry program in accordance with technical specification 6.85.c.

2. License condition 2.C. (13) Loss of Non-Class IE Instrumentation and Control System Bus During Operation This requirement can be deleted from the operating license. Revisions to the loss of bus voltage procedures have been completed.

3 License condition 2.C. (14), Engineered Safety Feature Reset Controls This requirement can be deleted from the operating license. TVA has completed the requirements of OI&E Bulletin 80-06 for Sequoy' ah Nuclear Plant.

4. License condition 2.C. (16).b regarding fire dampers and sprinklers This requirement can be deleted from the operating license. TVA has installed the fire dampers and replaced or relocated the sprinkler heads at Sequoyah Nuclear Plant.

5. License condition 2.C. (22). A, Safety Engineering Group This requirement can be deleted from the operating license. TVA haa an onsite Safety Engineering Group in accordance with technical specification 6.2.3

6. License condition 2.C. (22).B, Short-Term Accident Analysis and Procedure Revision This requirement can be deleted from the operating license. The Emergency Operating Instructions have been revised and the operators have been briefed on the changes.

7. License condition 2.C. (2.2).E, Auxiliary, Feedwater This requirement can be deleted from the operating license. The auxiliary feedwater pump endurance test has been completed and a report has been transmitted to the NRC (L. M. Mills' letter to A. Schwencer dated 11/4/80).

8. License condition 2.C. (22).F, Radiation Monitcrs

This requirement should be deleted from the operating license. Item

! II.E.4.2 of NUREG-0737 does not have a requirement for individual radiation monitors to isolate fluid lines. TVA's internal commitment j is to install such devices.- However, it is inappropriate to require l

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TVA to install the devices by a given deadline because such action is not required by NRC post-TMI requirements. TVA must have flexi-bility to procuro and install these devices within the constraints imposed by plant operation, design requirements, and procurement difficulties.

9. License condition 2.C. (23).B Plant Shielding This requirement can be deleted from the operating license. As noted in the Sequoyah shielding design review report, no additional shielding was required at Sequoyah (L. M. Mills' letter to A. Schwencer dated 6/16/80).

10. License condition 2.C. (23).C, Auxiliary Feedwater Initiation and Indication This requirement can be deleted from the operating license. The auto-matic initiation circuits at Sequoyah are safety grade. This fact was reported in TVA's response to NUREG-0578 for Sequoyah. The flow indication capability for Sequoyah was also described in the response to NUREG-0578. TVA believes the flow indication capability at ~

Sequoyah meets the requirements of NUREG-0737.

11. License condition 2.C. (23).D, Additional Accident Monitoring Instrumentation This requirement can be deleted from the operating license. Contain-ment pressure monitors that meet the requirements of the license condition have been installed at Sequoyah.

12. License condition 2.C. (23).E. Reactor Coolant System Vents The completion for this modification is scheduled before startup following the first refueling outage for Sequoyah unit 1. The reasons for scheduling this modification for the first refueling outage were transmitted to NRC in TVA's response to NUREG-0694 for Sequoyah  :

(L. M. Mills' letter to A. Schwencer dated 7/25/80). These reasons were found acceptable by NRC as noted in supplement No. 2 to the Safety Evaluation Report for Sequoyah Nuclear Plant. The license-condition should reflect the scheduled completion date.

. 13 License condition 2.C. (23).F, Post Accident Sampling Same reasons as above.

14. License condition 2.C. (23).G, Additional Accident Monitoring '

Instrumentation Same reasons as for 12 above.

15. License condition 2.C. (23).H, Instruments for Inadequate Coro Cooling Same reasons as for 12 above.

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