2CAN058809, Application for Amend to License NPF-6,addressing Qualified core-exit Thermocouple Requirements.Fee Paid
| ML20154N960 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/27/1988 |
| From: | Campbell G ARKANSAS POWER & LIGHT CO. |
| To: | Calvo J Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20154N964 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM 2CAN058809, 2CAN58809, GL-83-37, NUDOCS 8806030154 | |
| Download: ML20154N960 (5) | |
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s ARKANSAS POWER & LIGHT COMPANY CAPIT0L TOWER BUILDING /P. O B0X 551/LITTLE ROCK, ARKANSAS 72203/(501) 377 3525 T. GENE CAMPBELL May 27, 1988 vice President - Nuclear 2CAN058809 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn:
Mr. Jose A. Calvo, Director Project Directorate IV Division of Reactor Projects III, IV, V and Special Projects
SUBJECT:
Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6 NUREG-0737 Generic Letter 83-37 Technical Specification Change Request
Dear Mr. Calvo:
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l These proposed changes are in accordance with Generic Letter 83-37 Section II.F.2 (Inadequate Core Cooling Monitoring).
These changes specifically address qualified core-exit thermocouple requirements and affect section l _
3.3.3.6, Table 3.3-10 and Table 4.3-10.
Technical Specifications for the Reactor Vessel Monitoring System (RVLM) have not been addressed in this submittal.
RVLM System Technical Specifications were identified under the l
Technical Specification Improvement Program as not appropriate.
Currently this issue is being pursued through the B&W Owner's Group with NRC.
l Core-Exit Thermocouple (CET) requirements were edded to Section 3.3.3.6 Post-Accident Instrument Systems Section.
The proposed changes to Table 3.3-10 reflect the ICC channel operability requirements and limiting conditions for operation.
Changes to Table 4.3.10 reflect the surveillance requirements of the ICC Instruments.
The circumstances of this proposed Technical Specification amendment request are not exigent or emergency and are provided for the purpose of satisfying NUREG 0737 requirements as specified in Generic Letter 83-37.
Our letter dated January 2, 1987'(2CAN018701) informed NRC of the qualification test failure of the in-containment cabling and connectors for the core exit
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thermocouple system currently installed in AN0-2.
At that time, we indicated additional testing and evaluations on other designs would be 8806030154 880527 W\\t' JN}
PDR ADOCK 05000368 P
DCD MEMBEA M OOLE SOUTH UT8L8 TIES SYSTEM
l Mr. Jose A. Calvo May 27, 1988 performed.
We have completed the additional testing on a specific design which has successfully met all of the requirements.
Currently the ANO-2 core does not contain any qualified CETS.
We are scheduled to install a complete set of qualified CETS in the core during 2R6 which is currently in progress.
Since we cannot meet the specifications of these proposed changes until af ter 2R6, we request these changes not become ef fective until Cycle-7 operation which is scheduled for April 1988.
In accordance with 10CFR50.91(a)(1), AP&L has evaluated the proposed change using the criteria in 10CFR50.92(c) and has determined this change involves no significant hazards considerations.
Also, in accordance with 10CFR50.91(b)(1) a copy of this amendment request has been sent to Ms. Greta Dicus, Director, Division of Radiation Control and Emergency Management, Arkansas Department of Health.
A check in the amount of $150 is included as an application fee in accordance with 10CFR170.12(c).
Very truly yours, AY/n T. Gene Campbe 1 TGC:mb Attachments cc:
Ms. Greta Dicus, Director Division of Radiation Control and Emergency management Arkansas Department of Health 4815 West Markham Street Little Rock, Arkansas 72201
STATE OF ARKANSAS
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= COUNTY OF PULASKI
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I, T. Gene Campbell, being duly sworn, subscribe to and say that I am
- Vice President for Arkansas Power & Light Company; that I have full authority to execute this oath; that I have read the' document numbered 2CAN058809 and know the contents thereof; and that to the best of my
. knowledge, information and belief the statements in it are true.
96-T. Gene Campbell SUBSCRIBED AND SWORN T0 before me, a Notary Public in and for the County and State above named, this cSbay of
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f' 1988.
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Notary Public My Commission Expires:
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Description of Amendment Request These proposed cnanges are a result of NUREG 0737 requirements for inadequate core cooling concerns.
Following the May 1979 accident at Three Mile Island Unit 2, many feature requirements were added to nuclean power plants to enhance the ability of the operator to manage accidents and transients. -Qualified core exit thermocouples are one of the enhancements which serve to provide corroborative information to the operator during anticipated operating occurrences and accidents.
The proposed change adds to the Post-accident. Instrumentation Table 3.3-10 the requirements for the core-exit thermocouples.
Table 3.3-10 provides the required number of minimum operable channels and required operator action pursuant to specification 3.3.3.6.
A requirement of (2) operable core-exit thermocouple per core quadrant has been specified to meet the LCO.
The other change involved is to add a surveillance requirement for the core-exit thermocouples to Tabie 4.3-10.
The CETs have been assigned a monthly check and an 18 month calibration surveillance requirement.
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No Significant Hazards Consideration Determination The proposed changes to Sections 3.3.6 Tables 3.3-10 and 4.3-10 do not involve a significant hazards consideration because operation of Arkansas Nuclear One Unit-2 in accordance with these changes would not:
(1)
Involve a significant increase in the probability or consequences of an accident previously analyzed.
The core-exit thermocouples are neither credited nor required in the mitigation of any previously evaluated accident.
In addition, they are not relied upon for reactor trips or initiation of any plant safety systems.
This instrumentation is provided as another means for the operator to monitor inadequate core cooling conditions in accordance with the requirements of NUREG 0737.
(2) Create' the possibility of a new or different kind of accident from any previously analyzed.
The ICC instrumentation systems are utilized in the Emergency Procedures for corroboration of reactor coolant levels.
The proposed changes are intended solely to enhance the ability of the operator to monitor accidents and transients by providing the operator with additional corroborative information.
(3)
Involve a significant reduction in the margin of safety.
These specific proposed changes enhance accident and transient monitoring capability and therefore do not reduce the margin of safety.
The Commission has provided guidance concerning the application of the standards for determining whether a significant hazards consideration exists by providing certain examples of amendments that are considered not likely to involve significant hazards considerations.
Example (ii) relates to a change that constitutes an additional limitation, restriction or control not presently included in the technical specifications.
The proposed changes add additional accident monitoring instrumentation which is a requirement by the Nuclear Regulatory Commssions post-TMI-2 Action Plan.
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