ML20214N453

Informs That Util Will Complete Reinsp of All Nonconforming Piping in Accordance W/Generic Ltr 84-11 Guidelines at Next Scheduled Refueling Outage

ML20214N453
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	11/24/1986
From:	Taylor J DAIRYLAND POWER COOPERATIVE
To:	Zwolinski J Office of Nuclear Reactor Regulation
References
GL-84-11, LAC-11966, NUDOCS 8612030641
Download: ML20214N453 (3)

Text

t e

e.  %

D DA/RYLAND hhh[ COOPERATIVE P O. BOX 817

• 2615 EAST AVE SO LA CROSSE,WlSCONSIN 54602-0817 (608) 788-4000 JAMES W, TAYLOR Gineral Manager November 24, 1986 In reply, please refer to LAC-11966 DOCKET NO. 50-409 Mr. John Zwolinski, Director BWR Project Directorate #1 Division of Licensing U. S. Nuclear Regulatory Commission Washington, DC 20555

SUBJECT:

DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)

PROVISIONAL OPERATING LICENSE NO. DPR-45 GENERIC LETTER NO. 84-11 INSPECTIONS OF BWR STAINLESS STEEL PIPING

REFERENCES:

(1) NRC Letter, Zwolinski to Taylor, dated August 22, 1986.

(2) NUREG-0827, " Integrated Plant Safety Assessment Systematic Evaluation Program -

La Crosse Boiling Water Reactor."

(3) NRC Letter, Crutchfield to Linder, dated October 14, 1983.

(4) DPC Letter, Taylor to Eisenhut, LAC-9950, dated May 30, 1984 (5) Generic Letter 84-11, " Inspections of BWR Stainless Steel Piping", dated April 19, 1984.

Dear Mr. Zwolinski:

Reference 1 contained the NRC evaluation of Dairyland Power Cooperative's response to Generic Letter 84-11. The NRC letter requested that DPC provide a written commitment and schedule regarding reinspection of all non-conforming piping in accordance with the guidelines of Generic Letter 84-11 and revisions to reactor coolant system leakage surveillance.

DPC will complete the re-inspection of all non-conforming piping in accordance with the guidelines provided in Generic Letter 84-11 at the next scheduled refueling outage.

8612030641 861124 ADOCK 05000409 h p o A't WPl.6.10 PDR s G PDR 1

0 1

1 l

l Mr. John Zwolinski, Director November 24, 1986 ,

BWR Project Directorate #1 LAC-11966 1 Shortly before the issuance of Generic Letter 84-11, the NRC completed reviews of LACBWR's reactor coolant pressure boundary leakage detection capability.

These reviews were conducted under the auspices of the Systematic Evaluation Program Topic V-5 and in evaluation of proposed Technical Specification revisions resulting from NUREG-0313, Revision 1, " Cracking in Austenitic Stainless Steel Piping of BWRs." In the Safety Evaluation (Reference 3) of the Technical Specifications issued October 14, 1983, the NRC concluded that though DPC's proposed specifications differ from model specifications, they are acceptable. The Safety Evaluation notes "that the Systematic Evaluation Program has also evaluated the licensee's leakage detection capabilities in accordance with the more stringent Reg. Guide 1.45 and has determined that modifications are not required."

The Integrated Assessment of LACBWR (Reference 2) concluded that the leak detection sensitivity is considered acceptable, even though DPC does not explicitly calculate a leak rate so that 1 gpm would be detected within an hour. This conclusion was based on the following: the hourly recording of the reactor cavity and forced circulation pump cubicle particulate monitors' readings, the recording of the retention tanks' water accumulation every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, the calculation of the leakage rate to Containment based on retention tank level every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and that a leakage rate is calculated if a significant inexplicable increase is observed on either activity monitor. The particulate monitors have sufficient sensitivity to detect a leak rate of less than 1 gpm. The Integrated Assessment did, however, require that a procedure be prepared to identify actions necessary when leak detection is unavailable.

A procedure was prepared. Its requirements include that if the minimum monitoring requirements of the Technical Specification on Reactor Coolant System Operational Leakage cannot be met, the reactor be placed in the hot shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the cold shutdown condition within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

Based on the previous evaluations, the LACBWR reactor coolant system leakage surveillance should be coasidered acceptable. Additionally, since the Integrated Assessment evaluation was performed, control room indication of the retention tank levels has been installed and readings are now recorded hourly.

Since the activity monitors and tank level indicators are monitored hourly, a significant change would be observed within an hour.

DPC believes the procedural controls are adequate and additional Technical Specifications are not needed on monitoring frequency or inability to perform monitoring. The future goal is to simplify Technical Specifications.

Additional specifications should not be proposed unless necessary for plant safety and the health and safety of the public. Since the procedural requirements for hourly monitoring of reactor coolant system leakage detection instrumentation and for actions necessary if the minimum Technical Specification monitoring cannot be performed are already in place, new Technical Specifications are not needed.

WPl.6.10 November 24, 1986 Mr. John Zwolinaki, Director BWR Project Directorate #1 LAC- 11966 If there are any questions, please contact us.

Sincerely, l

- 1 I

l JWT:LSG:sks cc: Mr. Roby Bevan, LACBWR Project Manager Mr. James G. Keppler, Region III NRC Resident Inspector i

l A

WPl.6.10 -

3-

)

, - - - - -- , . - ..r-. - .n, men,- ,n- - , , , ,,me- ---v,w.,, ,s.w- ----,e- .