ML20054F181
| ML20054F181 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 06/09/1982 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.1.3, TASK-1.C.1, TASK-1.D.1, TASK-1.D.2, TASK-2.B.1, TASK-2.B.2, TASK-2.D.1, TASK-2.F.2, TASK-2.K.3.18, TASK-2.K.3.30, TASK-2.K.3.31, TASK-3.A.1.2, TASK-3.D.3.4, TASK-TM GL-82-10, LAC-8337, NUDOCS 8206150287 | |
| Download: ML20054F181 (6) | |
Text
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[k COOPERAT/VE pO Box si7 2615 EAST AV SOUTH. LA CROSSE. WISCONSIN 54601 June 9, 1982 (608) 788-4000 In reply, please refer to LAC-8337 DOCKET NO. 50-409 U. S. Nuclear Regulatory Commission AITN: Mr. Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation Division of Operating Reactors Washington, D. C.
20555
SUBJECT:
DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)
PROVISIONAL OPERATING LICENSE N0. DPR-45 POST-TMI REQUIREMENTS (GENERIC LETTER 82-10)
REFERENCES:
(1) NRC Letter, Eisenhut to All Licensees of Operating Power Reactors, dated May 5,1982 (2) DPC Letter, Linder to Crutchfield, LAC-8180, dated March 26, 1982 (3)
DPC Letter, Linder to Ziemann, LAC-6705, dated December 20, 1979
~
(4)
DPC Letter, Linder to Denton, LAC-6769, dated January 31, 1980 (5)
DPC Letter, Linder to Denton, LAC-7266, dated December 5, 1980 (6)
DPC Letter, Linder to Eisenhut, LAC-7624, dated June 24, 1981 (7)
DPC Letter, Linder to Crutchfield, LAC-7834, dated September 19, 1981 (8)
DPC Letter, Linder to Eisenhut, LAC-7684, dated July 22, 1981 (9)
DPC Letter, Linder to Eisenhut, LAC-8329, dated June 7,1982
=
(10) DPC Letter, Linder to Eisenhut, LAC-7564, dated May 21, 1981 (11)
DPC Letter, Linder to Eisenhut, LAC-7196, dated October 31, 1980 (12)
DPC Letter, Linder to Crutchfield, LAC-7790, dated September 14, 1981 Gentlemen:
Your letter (Reference 1) requested commitments to the timely implementation of certain Post-TMI Items identified in NUREG-0737. Attachment 1 to this letter lists the items identified in Enclosure 1 of your letter and contains the information requested or other explanations.
. Oh WP-1 8206150287 820609 PDR ADOCK 05000409
Mr. Darrell G.~ Eisenhut, Director June 9, 1982 U. S. Nuclear Regulatory Commission LAC-8337 An extension of time to respond to the request until ' June 11, 1982 was granted by R. Dudley, NRR/NRC on June 4,1982.
If there are any questions concerning this response please contact us.
Very truly yours, DAIRYLAND POWE ~C0 OPERATIVE Frank Linder, General Manager FL:JDP:eme Attachment cc:
J. G. Keppler, Dir., NRC-DR0 III NRC Resident Inspector WP-1. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
ATTACHMENT 1 LICENSEE RESPONSE TO NUREG-0737 ITEMS ITEM STATUS I.A.1.3.1 An administrative procedure governing the assignment of overtime was initially issued on October 31, 1980.
It was subsequently revised on March 23, 1982. A further revision of this procedure in accordance with an NRC Policy Statement issued by Generic Letter No. 82-02, dated February 8,1982 will be impleniented by June 30, 1982.
I.A.1.3.2 A request for an exemption to minimum shift crew staffing has been filed (Reference 2).
The proposed alternative would have staggered implementation dates of July 1, 1982 and July 1, 1983 and requests a minimum crew size of eight individuals rather than the ten individuals specified in Page 3-9 of NUREG-0737.
No changes to Technical Specifications have been submitted at this time.
I.C.1 The review and modification of procedures to respond to transients and accidents was requested as a part of Item 2.1.9 of NUREG-0578.
Item 2.1.9 of NUREG-0578 contained three recommendations or priorities for analyses. These priorities were:
(1) Analysis of small break loss of coolant accidents.
(2) Analysis of the symptoms of inadequate core cooling and required actions to restore core cooling; and (3) Analysis of transient and accident scenarios including operator actions not previously analyzed.
Item I.C.1 of NUREG-0737 combine these elements.
As the La Crosse Boiling Water Reactor is a unique facility (the only one manufactured by Allis Chalmers) currently in operation, no generic guidelines for procedure development were prepared following clarification by the NRC.
l Additionally, the NRC did not prepare a NUREG addressing the I
issue of small break LOCA's at LACBWR as it did for the four nuclear steam suppliers; NUREG-0565 & 0667 - Babcox and Wilcox NUREG-0611
- Westinghouse Co.
- General Electric Co.
- Combustion Engineering Co.
WP-1 l
o ITEM STATUS I.C.1 DPC has submitted the review of small break loss of coolant (Continued) accident analysis (Reference 3).
DPC has submitted the analysis of inadequate core cooling used to modify the operating procedures for recognition by operating personnel of inadequate core cooling (Reference 4) and implemented a procedure modification. DPC has submitted a review of plant accident and transient analysis (Reference 5) and implemented procedure modifications.
DPC will complete the review of procedures and modifications as necessary once the NRC has responded to the submitted analysis reviews (References 3, 4 and 5).
The recommended schedule of the first refueling after October 1,1982 can not be committed to without receiving the staff response at least 1 year ahead of implementation schedule.
I.D.1 Under development by NRC; no reply needed at this time (Reference 1).
I.D.2 Under development by NRC; no reply needed at this time (Reference 1).
II.B.1 DPC has requested that the NRC find the Manual Depressurization System Valves a fulfillment of these requirements (Reference 6). Any modifications required will be scheduled once the NRC response has been received. No changes to Technical Specifications have been submitted at this time.
II.B.2.3 DPC identified certain specific electrical equipment in a harsh environment which performs safety related functions which would be replaced by June 30, 1982.
(Reference 11). Of the twenty-one (21) solenoid valves identified for replacement two (2) valves (Item 11) will not be replaced by June 30, 1982.
One of the three (3) reactor water level transmitters, (Item 43, #50-42-306) will not be replaced by June 30, 1982.
The replacement cable for the containment high range radiation monitors (Items 29 & 30) may not be replaced by June 30, 1982.
WP-1 a.
ITEM STATUS II.B.2.3 DPC identified certain additional items to be replaced by June (Continued) 30, 1982 (Reference 3) following NRC review of Reference 12.
This letter also notified the NRC that replacement of high pressure core spray pump motors (Item 44 of Reference 11) could not be accomplished until the 1983 refueling outage at the earliest.
DPC identified (Reference 12) an alternate containment building cooling method and committed to a review of the electrical and mechanical features of the system (which is in a mild environment) by June 30, 1982. We have been unable to complete this review at this time.
DPC identified (Reference 12) the requirement to establish a preventative maintenance and testing program to address aging of compnnents as part of the environmental qualification program.
This will not be completed by June 30, 1982.
A list identifying equipment performing safety-related functions which is located in mild environments has been completed, however; the evaluation and documentation on this equipment is not assembled.
The preceeding items constitute DPC response to CLI-80-21 (NUREG-0737, Page II.B.2.6).
The Nuclear Regulatory Commission is currently considering proposed rule 10 CFR 50.49 as published in the Federal Register January 20, 1982, (47FR2876) which establishes a new time schedule for completion of environmental qualifications. This document has received Advisory Committee on Reactor Safety endorsement. DPC will establish a schedule for resolution of this item once NRC action on 10 CFR 50.49 is completed.
11.0.1.2 Applicable only to PWR's (Reference 1).
II.D.1.3 Applicable only to PWR's (Reference 1).
II.F.2 Under development by NRC, no reply needed at this time.
(Reference 1).
II.K.3.18 LACBWR does not have an Automatic Depressurization System.
d WP-1 l
ITEM STATUS II.K.3.30/31 The small break LOCA analyses have been submitted to the NRC for a review (Reference 7) to determine if any revision is required.
Any model modification or reanalysis required would be scheduled after the finalization of NRC review of the previous analysis.
III.A.1.2 A request for exemption to augmentation of staffing has been submitted to the NRC.
(Reference 9).
III.A.1.2 Modifications to the Technical Support Center and Emergency Operations facility similar to those proposed by Reference 10 are underway and the majority of the system is expected to be completed by October 1982. The major changes in the improved design include installation of a transient interruptible power suppy (UPS) for the computer and transmitting analog signals directly to a PDP 11/24 Digital Equipment Corporation computer, rather than routing the signals through an Autodata System to an ND6600 computer. Upon completion of the Control Roon Habitability Study, DPC reported (Reference 8) that the previously proposed ventilation system modifications (Reference
- 4) were not necessary and so would not be implemented.
III.A.2.2 DPC has installed a new ten-meter tower in a relocated site.
The tower provides windspeed, direction and temperature.
The readouts from the ten-meter tower and top of stack for windspeed and direction and AT as well as ten meter ambient temperature will be available on printout in the Guergency Operations Facility and Technical Support Center by October 1, 1982.
III.D.3.4 The LACBWR Control Room habitability study was completed and submitted to the NRC (Reference 8).
The modifications proposed in this submittal will be completed by January 1, 1983. No changes to Technical Specifications have been submitted at this time or are planned.
WP-1