ML20212N461
| ML20212N461 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 08/22/1986 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | Taylor J DAIRYLAND POWER COOPERATIVE |
| Shared Package | |
| ML20212N463 | List: |
| References | |
| GL-84-11, TAC-56859, NUDOCS 8608280242 | |
| Download: ML20212N461 (3) | |
Text
.
UNITED STATES 8
NUCLEAR REGULATORY COMMISSION n
T 4
E WASHINGTON, D. C. 20555 k..... p8 August 22, 1986 Docket No. 50-409 Mr. James W. Taylor General Manager Dairyland Power Cooperative 2615 East Avenue South La Crosse, Wisconsin 45601
Dear Mr. Taylor:
SUBJECT:
EVALUATION OF DAIRYLAND POWER COOPERATIVE RESPONSE TO GENERIC LETTER 84-11 FOR STAINLESS STEEL PIPE INSPECTION (TAC 56859)
Re:
La Crosse Boiling Water Reactor (LACBWR)
On April 19, 1984, the staff issued Generic Letter (GL) 84-11 " Inspections of 4
BWR Stainless Steel Piping," to all licensees of operating boiling water reactors (BWRs) including La Crosse.
In the GL, the staff stated that inspections conducted at several BWRs revealed intergranular stress corrosion cracking (IGSCC) in large-diameter recirculation and residual heat removal stainless steel piping. These inspections were conducted pursuant to either IE Bulletins 82-03, Revision 1 or 83-02.
It is the position of the Office of Nuclear Reactor P.egulation that the results of these inspections mandate an ongoing program for similar reinspections at LACBWR. The staff provided guidance in the GL as to what an acceptable reinspection program should include.
By letter dated May 30, 1984, Dairyland Power Cooperative (DPC) submitted a response to GL 84-11 for LACBWR. Our staff has completed its evaluation of all of your submittals to date regarding GL 84-11 for LACBWR. Our staff concludes that your response in the area of piping inspection and leak detection did not meet the requirements of GL 84-11. The detailed staff evaluation of your responses to GL 84-11 is enclosed.
Concerning the scope of planned inspections, DPC stated in its May 30, 1984 letter that piping inspections would follow LACRWR Technical Specification 3.0.10(f) (Inservice Inspection Requirements). The staff noted in an earlier submittal dated July 10, 1980 that DPC classified several nonconforming pipelines in the decay heat, main steam and feedwater systems as nonservice j
sensitive and, therefore, those pipelines were not included in the augmented inspection program of Technical Specification 3.0.10(f). GL 84-11 states that nonservice sensitive piping no longer exists, because all nonconforming piping is considered to be service sensitive.
$$[
ObN b 0 G
James W. Taylor 2-August 22, 1986 Therefore, the staff is requesting DPC to provide a written commitment.and schedule within 90 days of receipt of this letter to reinspect all nonconforming piping in accordance with the guidelines provided in GL 84-11.
The staff also found the LACBWR technical specifications for reactor coolant leakage'surveill'ance requirements were not in accordance with GL 84-11.
The unidentified reactor coolant leakage limit inside the containment is I gpm at LACBWR which is more restrictive than the augmented leakage limit of 2 gpm increase in a 24-hour period. However, the benefit of this lower leakage limit is reduced, because the technical specification requires monitoring of the leakage only once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and also does not define an inoperability period for the sump level and flow rate monitoring system.
Therefore, the staff is also requesting DPC to provide a written commitment and schedule within 90 days of receipt of this letter to change the current reactor coolant system leakage surveillance to conform to the leakage surveillance requirements in GL 84-11. This schedule should include the proposal of appropriate Technical Specifications to incorporate these require-ments.
Items 4.0 and 5.0 in the enclosed evaluation have been provided for your guidance.
Sincerely, QRIGINAL SIGNED BY John A. Zwolinski, Director BWR Pro.iect Directorate #1 Division of BWR Licensing
Enclosure:
Safety Evaluation cc w/ enclosure:
See next page DISTRIBilTION 4 Docket file a RBernero NRC PDR OGC.Beth (Info enly) local PDR EJordan BWD#1 Reading BGrimes CJamerson
~
JPartlow JStang NThompson JZwolinski ACRS, 10 WKoo Lacrosse file GHolahan
/
OFC : DBL:PD#1
- DBL: F D#1
- C/PD#1/ DBL :
j'g,(/dn a_
NAME :CJamerson@
- J 6
- JZwolinski DATE:8/13/86
- 8/lf/86
- 8/Tt'/86
Mr. Ja'nes W. Taylor Dairyland Power. Cooperative la Crosse Boiling Water Reactor cc:
Fritz Senubert, Esquire Mr. Lanning Smith, Chief Engineer Staff Attorney Wisconsin Public Service Commission Dairyland Power Cooperative Post Office Rox 7854 2615 East Avenue South Madison, Wisconsin 53707 La Crosse, Wisconsin 54601 Roy P. Lessy, Jr.
O. S. Heistand Morgan, Lewis A Bockius 1800 M Street, N.W.
7th Floor North Receptionist Washington, D.C.
20036 Mr. John Parkyn, Plant Manager La Crosse Boiling Water Reactor Dairyland Power Cooperative P. O. Box 275 Genoa, Wisconsin 54632 U.S. Nuclear Regulatory Commission Resident Inspectors Office Rural Route #1, Box 276 Genoa, Wisconsin 54632 i
Town Chairman Town of Genoa Route 1
~
Genoa, Wisconsin 54632 l
Chairman, Public Service Commission of Wisconsin Hill Farms State Office Building Madison, Wisconsin 53702 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 l
..--.-.