ML19341D194
| ML19341D194 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 01/21/1981 |
| From: | Linder F DAIRYLAND POWER COOPERATIVE |
| To: | Heishman R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML19341D188 | List: |
| References | |
| LAC-7348, NUDOCS 8103050100 | |
| Download: ML19341D194 (6) | |
Text
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'D DA/RYLAND h
h COOPERA7/VE. eo eox si7 2 sis EAST AV SOUTH. LA CROSSE. V.15CONSIN 64001 (6C8) 7884000 January 21, 1981 In reply, please refer to LAC-7348 DOCKET NO. 50-409 Mr.
R. F. Heishman Chief, Reactor Operations and Nuclear Support Branch U. S. Nuclear Regulatory Commission Directorate of Regulatory Operations Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137
SUBJECT:
DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBNR)
PROVISIONAL OPERATING LICENSE NO. DPR-4 5 IE INSPECTION REPORT NO. 50-409/80-14
References:
(1)
NRC Letter, Heishman to Linder, dated December 23, 1980.
(2)
Gulf United Report SS-867, "A Recommendation for Modification of the LACBWR Bypass Valve Control System", September-October, 1971.
Dear Mr. Heishman:
This letter constitutes the written statement required in reply to the November 1980 NRC Inspection Report (Reference 1) which we received December 29, 1980.
Appendix A,
listed four items of noncompliance.
ENFORCEMENT ITEMS Infraction:
"1.
LACBWR Technical Specification 4.2.5.7 states:
"Except during plant startup and shutdoun, the main steam bypass valve control chall be set to begin opening the bypass valve at an indicated prescure corresponding to a turbine intet precoure not more than 15 pei above its nominal value."
Contrary to the above, on Sep ternber 15, 1980, uith the reactor at stead 5 state pouer and on September 16, 1980, uith the reactor at steady state pouer, the resident inspectors noted that the main steam bypaso valve control uas set to begin open-ing the bypass valve at 19 psi, and 17.5 poi, recpectively."
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Mr. R. F.
Heishman LAC-7348 Chief, Reactor Operations and January 21, 1981 Nuclear Support Branch DPC RESPONSE:
Corrective Action Taken and Results Achieved:
On September 16, 1980, the narrow range bypass valve controller setting on the benchboard was reduced to 15 psi above actual steam pressure as measured in the alternate core spray line near the reactor vessel head.
Fxcept during plant startups and shutdowns, the setting has been maintained at approximately 15 psi since then.
Since the plant had formerly operated (through mid-1971) with reactor pressure at 1265 psig with the main steam bypass valve set-point at 1280 psig, the fact that the main steam bypass valve set-point was found to be 19 psi above approximately 1250 psig indicates that the occurrence was not of safety significance.
Corrective Action Taken to Avoid Further Noncompliance:
At 0900 on October 15, 1980, the turbine operator commenced recording the bypass valve setting hourly on Log L-82, " Turbine-Generator Plant Log".
Usage of a revised Log L-82 started at 0001 on November 11, 1980.
The main steam bypass valve Narrow Range Deviation is printed on this revision as one of the routine hourly readings.
This should prevent any operators from forgetting to record the bypass valve setting.
The Log also has printed on it the specification of <l5.
Date Full Compliance Achieved:
November 2, 1980.
Infraction:
"2.
LACBWR Technical Specification 3.8.1 states:
" Written procedures and administrative policies shall be ca tablished, implemented and maintained.... "
Contrary to the above, licensee personnel failed to properly complete the chift turnover log required by Administrative Control Procedure (A CP) 2.3 on November 10, 22, 12, 17, 18, 25 and 27, 1980."
DPC RESPONSE:
Corrective Action Taken and Results Achieved:
Licensee personnel did not properly complete the shif t turnover check-off list contained in the governing Administrative Control Procedure for Shift Transition due to a misunderstanding of the
. I i
a Mr. R. F. Heishman LAC-7348 Chief, Reactor Operations and January 21, 1981 Nuclear Support Branch procedure.
The plant was in Operating Condition 3,.4, or 5 on
~the dates mentioned above.
The requirement for completion of the shift turnover log has been clarified to.the operators and the log is now being completed as per procedure.
Corrective Action to Avoid Further Noncompliance:
The Control Room Log Book stamp will be modified to include a position for logging the Operating Condition at the beginning of each shift.
Once this has been accomplished, ACP 2.3 will be re-vised to require the Shift Turnover Check-Off List be used only during Operat'ag Conditions 1 and 2.
This revision should prevent operators from neglecting to complete the turnover list at all times it is required.
Date Full Compliance Achieved:
November 28, 1980.
Infraction:
"3.
LACBWR Technical Specification 3.8.1 states:
"Each procedure and administrative policy of 3.8.1 above, and changes thereto, shall be revieved by the ORC and approved by the Plant Superintendent prior to implementation and every too years thereafter."
Contrary to the above, on November 14, 1980, the licensee per-connel vere performing refueling operations utilizing procedures in Volume VI of the LACBWR Operating Manual that had not re-ceived the required tuo year revieu."
DPC RESPONSE:
Corrective Action Taken and Results Achieved:
All sections of Volume VI of the LACBWR Operating Manual had received their two-year review as of November 14, 1980, as found by a complete review of the records, however, a temporary change existed in Section 4 since February 1978 that had been overlooked.
This tempor-ary change was re-reviewed by the ORC on November 14, 1980, and no revision was necessary..
r Mr.
R. F. Heishman LAC-7348 Chief, Reactor Operations and January 21, 1981 Nuclear Support Branch Corrective Action Taken to Prevent Further Noncompliance:
A second review.which included a permanent change was made to Section 4 on November 16, 1980.
This change which incorporated the temporary change, was reviewed by the ORC and approved by the Plant Superintendent on December 4, 1980.
Date Full Compliance Achieved:
December 4, 1980.
Infraction:
"4.
LACBUR Technical Spccification 3.8.1 ctates:
" Written procedures and adminictrative policico chall be ca tablished, implemented and maintained... "
Contrary to the above, licenece personnel failed to monitor cource range indication during fuel movement in the reactor veccel, on November 18 and 19, 1980, as required by Volume VI of the LACBUR Operating Manual and Fuel Transfer Procedure No. FC 8 0- 1, Procedurc No.
2.
Contrary to the above, the Control Room Accountability Watch failed to initial any entries made on his vatch for fuct transfere on cuing chift November 18, 1980.
Contrary to the above, the briefing book for fuel movement, utiliced by operator 9 to verify a prercquicite to fuct move-ment as required by Volume VI of the LACBWR Operating Manual, had erroneouc information in that it stated the minimum cater level in the Fuel Elcment Storage Well above fuel racks to be tuo feet uhile the LACBWR Technical Specification is 16 feet above the fuel."
DPC RESPONSE:
Corrective Action Taken and Results Achieved:
On November 18 and 19, source range readings were observed and re-corded hourly on Log L-83, " Reactor Plant Log".
These readings showed the count rare was decreasing as fuel was removed from the reactor, as expected.
A temporary change was made to the procedure and approved by the ORC on November 19, 1980, specifying that the source range instruments need to be monitored during fuel loading rather than durina all fuel movements.
The source ranae instruments were monitored during fuel additions to the reactor.
~
1hr.
R.
F. Heishman' LAC-7348 Chief, Reactor Operations and January 21, 1981 Nuclear. Support Branch i
Although the Fuel Element Transfer Record (Form 1) copy kept in the Control Room was customarily initialed by the Control Room operator as fuel element transfers were performed and later signed by the Accountability Delegate, there was no specific procedural requirement for these initials and signatures.
The completion and initialing of the form by the Accountability Delegate in the fuel handling area is required by procedure and this was accomplished.
There are two sections of Technical Specifications which discuss water level relative to irradiated fuel:
4.2.8.3 "During the handling and storage of irradiated fuel elements that have been operated at power levels greater than 1 MWt, the depth of water in the reactor upper cavity and/or spent fuel storage well shall be at least 2 feet above the active fuel."
2.12.5 "The fuel storage well level shall be at least 16 feet above any fuel stored in the spent fuel storage rack."
Section 4.2.8.3 was recited verbatim in the memorandum of the Assis-tant to Operations Supervisor dated November 12, 1980, which was contained in the briefing book.
s Corrective Action Taken to Prevent Further Noncompliance:
The temporary change to Volume VI of the Operating Manual was incor-porated into a permanent revision and approved by the Operations Review Committee on December 4, 1980.
Date Full Compliance Achieved:
1 November 19, 1980.
An extension for submittal of this letter was granted to Mr. R. Shimshak by W. Forney, NRC Resident' Inspector, on January 15, 1981.
If you have any questions, please contact us.
Very truly yours, DAIRYLAND POW R COOPERATIVE s
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Frank Linder, General Manager FL:LSG:af cc:
NRC Resident Inspectors 1
.Mr. R. F. IIeishman LAC-7348 Chief, Reactor Operations and January 21, 1981
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i Nuclear Support Branch i
STATE,OF WISCONSIN.)
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COUNTY OF LA CROSSE)
Personally came before me this E day of January, 1981, the above named Frank Linder, to me known to be the person who executed the foregoing instrument and acknowledged the same.
T, Notary Puplic, La Crosse County, Wisconsin.
My Commission Expires 2/26/84.
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