IR 05000409/1987008

Insp Rept 50-409/87-08 on 870415-0530.No Violations Noted. Major Areas Inspected:Licensee Actions on Previous Insp Findings,Operation Safety Verification,Monthly Maint & Surveillance Observations,Ler Followup & IE Info Notices

ML20215G738
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	06/12/1987
From:	Jackiw I NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20215G709	List: IR 05000409/1987008 ML20215G707
References
50-409-87-08, 50-409-87-8, IEB-85-003, IEB-85-3, IEIN-87-008, IEIN-87-010, IEIN-87-012, IEIN-87-10, IEIN-87-12, IEIN-87-8, NUDOCS 8706230367
Download: ML20215G738 (8)

Text

__ - - _ - _ _ _ - _ - _ _ _ _ _ _ _ _ _ _

l

.

L1 .

..

V

'

O.S. NUCLEAR REGULATORY COMMISSION

REGION III

. Report. No.. 50-409/87008(DRP)

Docket No. 50-409 License No. DPR-45 Licensee: Dairyland Power Cooperative 2615 East Avenue - South La Crosse, WI 54601 Facility Name: L'a Crosse Boiling Water Reactor Inspection At: La Crosse Site, Genoa, WI i

Inspection Conducted: ; April 15, 1987 through May 30, 1987-Inspector: K. R. Ridgway  ;

i

'"

. Approved By: 1. blac w, f -/2 ~ /'7 Reactor Proj, ts Section 2C Date j

'

Inspection. Summary Inspection on April 15, 1987 through May 30, 1987 (Report No.50-409/87008(DRP)) )

Areas Inspected: . Routine, unannounced inspection by the resident inspector 4 of Licensee Actions on Previous ' Inspections Findings; Operational Safety Verification; Monthly Maintenance Observation;' Monthly Surveillanc Observation; Licensee Event Reports Followup; Transportation; Organization.

,

and Administration; and IE Information Notices Results: No violations were identifie l L

L L

%

8706230367 70612 9 DR ADOCK05gO 4-

'

_ __ _ _ _ _ _ _ __ _ _ _ _ -___ _ ___ _ _ _ _ _ _ _ _ _ ._ _ _ _____ _ _

.

a

'lV

. DETAILS 1. Persons Contacted

• J. Parkyn, Plant Superintendent

• Boyd,.0perations Supervisor L. Kelley, Assistant-to Operations Supervisor L. Nelson, Health and Safety Superviso'r

• R. Wery, Quality Assurance Supervisor-L. Goodman,. Operations Engineer D. Rybarik, Mechanical Engineer The inspectors also interviewed other licensee personnel during the course of the inspectio * Denotes those' attending exit interviews during the inspection perio . General-On April 24,1987,- the. Dairyland Power Cooperative (DPC)- Board authorized the permanent shutdown of LACBWR due to economic reasons. The facility is now in cold shutdown condition with fuel still in.the' vessel. The licensee plans to defuel.the reactor starting June l'and to complete the operation by June 15, 198 Fuel. handling will be conducted only on the 8-4 shift. Maintenance work continues on all safety-related. items. Any maintenance work cancelled on unneeded safety equipment will be referred to the Operatior.s Review Committee for its review and concurrence. Shift wise staffing meets the existing Technical Specification (TS) and Security Plan requirements for cold shutdown with fuel in the vessel. Operators, craftsman and guard training continues to meet the TS requirement All required surveillances are being completed on schedule if they can be conducted during cold shutdown. The security-safeguard plans are being maintained at normal level On May 22, 1987, the licensee submitted a proposed amendment.to change the license from an operating license to a license to possess - onl . Licensee Actions on Previous Inspections Findings In light of the facility shutdown, open or unresolved items and bulletins I have been reviewed to determine whether additional inspection effort is justified or whether they should be administrative 1y closed. Based on the reviews, the following open items are administratively close /85003-BB: IE Bul.letin 85-03 - Motor Operated Valve Common Mode

,

Failures During Plant Transient i 2 l l

I

.

. /84009-14: Open Item - IPSAR Reference 4.21.3.2, Lock-Closed Valves 55-24-1 and 62-28-013 and Install a Remotely Operated Solenoid Valve Outside Containmen /84009-17: Open Item - IPSAR Reference 4 21.5, Develop Procedures to Specify Under Which Conditions /su;te Manual Valves Will be Closed. Licensee to install two check valves in serios in the sample lin /84009-18: Open Item - IPSAR Reference 4.26.4, Provide Separate Power Supplies for the Full Scram Channels, /850XX-01: Open Item - Unusual Eve'nt Declared 4/21/85 Due to Leak in Seal Water Supply (Closed in LER 85009). /850XX-02: Open Item & Unusual Event Declared 10/22/85 Due to Maintenance Personnel in Switchyard Inadvertently Tripping Breakers

- Normal Scram - All Rods Inserted - Diesels Started (Closed with LER 85017 and IR 409/86017). (Closed) 409/860XX-01: Open Item - Unusual Event Declared Due to Manual Scram During Startup While in Heatup Mod Other open item or unresolved item closures are as follows: (Closed) 409/84012-02: Violation Severity Level 5 - Document Control Program Not Folle;wed. The licensee has reviewed the mechanical electrical and engineering files and have removed old or installed current drawings. A memo was distributed reiterating the importance of maintaining design document files in a current statu . (Closed) 409/84012-08: Open Item: Out-Of-Calibration Tools and Equipment are Not Evaluate Procedure ACP-13.1 Item 4.4 has been added to include the evaluation on tests or calibrations made with equipment subsequently found be to out of calibration and to require retesting or calibration if any tests are in doub (Closed) 409/84012-09: Open Item - No System to Add New Equipment to the Inventory List and Calibrat Procedure ACP-13.1 Item has been added to assign responsibility to each department to maintain a current listing of all measuring and test equipment used by their departmen k. (Closed) 409/85003-01: Unresolved Item - Failure of Safety Review Committee to Review Minutes of the Operations Review Committee and the Other Review Requirements of Section 6.5.2.7 of the Technical Specifications (TS). A review of the minutes of the last four SRC meetings indicated the review of the ORC minutes and other TS requirements were being in 1uded in the ORC review .

3 (Closed) 409/85006-01: Open Item - Quality Assurance Record Storag Current surveillance records are duplicated to maintain a current file in the plant while the originals are placed in vault file (Closed) 409/85006-02: Open Item - Safeguards Report Evaluatio The Updated Final Safety Analysis issued in June 1986 no longer refers to' tagging of valves associated with the fuel pool. -LACBWR Operating Manual Volume II Section 11.4 Operating Procedures, revised in July 1986, gives proper valving instructions and valve position i (Closed) 409/85017-01.: Open Item - Verify Acceptability of Licensee Assigned Instrument Accuracy Acceptance Criteria. The licensee has completed a list showing the acceptance criteria for all instruments .

used at LACBW I (Closed) 409/85017-02: Open Item - Verification of Points Used for Vibration Measurements per ASME Code. The licensee develtped a Special Procedure OPS 66-01, Evaluation of Vibration Measurement Locations,_to determine the point of highest vibration anc this point has been determined and marked on all pumps requiring vibration measurement (Closed) 409/85017-04: Open Item - Documenting Stopwatch I.' Numbers in Plant Procedures Requiring Times. The licensee has revised all procedure check lists to include the stopwatch 1. . Operational Safety Verification The inspector observed control room operations, reviewed applicable logs and conducted discussions with control room operators. The inspector verified the operability of selected emergency systems, reviewed tagout records and verified proper return to service of affected component Tours of the crib house, reactor building, and turbine building were conducted to observe plant equipment conditions, including potential fire hazards, fluid leaks, and excessive vibrations and to verify that

.

maintenance requests had been initiated for equipment in need of maintenance. By observation and direct interview the inspectors verified f that the physical security plan was being implemented in accordance with !

the station security pla l The inspector observed plant housekeeping / cleanliness conditions and t verified implementation of radiation protection controls. The inspector walked down the accessible portions of the Decay Heat Removal System, Primary Purification System, and Fuel Storage Well Cooling System to verify operabilit l

J

.

.

These reviews and observations were conducted to verify that facility operations were in conformance with the requirements established under technical specifications,10 CFR, and administrative procedure ~No-violations were identifie . Monthly Maintenance Observation Station maintenance activities of selected safety-related systems and components were observed / reviewed to ascertain that they were conducted in accordance with approved procedures, regulatory guides and industry codes or standards and in conformance with technical specification The following items were considered during this review: the limiting conditions for operation were met while components or systems were removed from service; approvals were obtained prior to initiating the work; activities were accomplished using approved procedures.and were inspected as applicable; functional testing and/or calibrations were performed prior to returning components or systems to service; quality control records were maintained; activities were accomplished by qualified personnel; parts and materials used were properly certified; <

radiological controls were implemented; and, fire prevention controls were implemente Work requests were reviewed to determine status of outstanding jobs and to assure that priority was assigned to the maintenance of safety-related equipment which could affect system performanc No violations were identifie . : Monthly Surveillance Observation i

On April 24, 1987, the inspector observed technical specifications )

required quarterly inservice testing on the Shutdown Condenser Inlet j Valves 1A and 18 and Offgas Vent Valves and verified that testing was l performed in accordance with adequate procedures, that test I instrumentation was calibrated, that limiting conditions for operation were met, that removal and restoration of the affected components were accomplished, that test results conformed with technical specifications and procedure requirements and were reviewed by personnel other than the individual directing the test, and that any deficiencies identified I during the testing were properly reviewed and resolved by appropriate l management personnel, l

!

The initial test of the IB Inlet Valve did not meet the ASME Chapter XI )

Code requirement by exceeding the permitted 50% full-stroke time increase over the previous test stroke time for valves having stroke times less than 20 seconds. When the stroke time exceeds this limit, the test i frequency must be increased to once each month and maintained at this ;

.

.

frequency until maintenance is performed on the valve. The licensee immediately established the required monthly test frequency; however, on April 27 the control air line to this valve was found to be leaking and following repairs,-the IB Inlet. Valve failed the required post :

maintenance operability test by sticking partially open. Failure o the IB valve placed the facility in a 72-hour action statement. Since the plant was already scheduled to shutdown permanently within two weeks (see Paragraph 2), the shutdown was completed early before the action statement expire No violations were identifie . Licensee Event Reports Followup Through direct observations, discussion with licensee personnel, and review of records, the following event reports were reviewed to determine that reportability requirements were fulfilled, immediate corrective actions were accomplished, and corrective actions to prevent recurrence had been accomplished in accordance with technical specifications, (Closed) LER.87-001: Reactor Scram. Turbine Stop Valve Partial Closure During Simulated Overspeed Test. . This LER was described in IR 409/87003 and was being held open pending licensee evaluation to determine if an operations manual revision was required. The evaluation concluded that revision was not required and the turbine stop valve push button was not painted red due to the permanent shutdown status, (Closed) LER 85-09: Seal Inject System Leak with Scram During Shutdown. The LER, described in IR 409/85012 and 409/85022, was held open pending the replacement of the flexible stainless steel hoses between the flow orifice and the transmitters. The Facility Change for this work was cancelled due to the permanent shutdown statu (Closed) LER 86-07: Unlatched Control Rod. This LER, described in IR 409/86006, was held open pending refueling procedure changes and operator training. These have been cancelled due to the permanent shutdown statu ' (Closed) LER 86-18: Reactor Scram Due to Relay Malfunction /Line Separation at Reactor Water Level Transmitter. This LER, described in IR 409/86009, was held open pending the completion of operator training on failures of this typ The training has been complete ) (Closed) LER 86-38: Boron Tank Solution Concentration Below Technical Specification Limit. This LER, described in IR 409/86017, was held open pending valve maintenance and test procedure chang l l

l 6  !

i i

.

The licensee developed special procedure,.0PS 60-01, to test valves 60-25-001.and 005 following the startup testing. The permanent test procedure change.and valve maintenance will not be completed due t the shutdown statu (Closed) LER 86-22: Decay Heat Line Cracks. This LER, described in IR 409/86009, was held open pending NRR's review and examination of a .section of pipe which was sent to Brookhaven Laboratory. The licensee had been planning to do further ISI on this system, but since LACBWR is now shutdown, they are closing out all work on this proble (Closed) LER 85-16: Reactor Scram, Fuse 32-1 Shorted During Recorder Maintenance. Actions taken for this LER, described in 4 IR 409/85018, were found to be acceptable, but the LER was held open pending further evaluation by the licensee. Since LACBWR i is in shutdown status, no further work will be don . IE Information Notices e j For the IE Information Notices listed below, the inspector verified that

.they were received by licensee management and reviewed for their ,

applicability to LACBWR. In addition, the inspector verified that the l licensee had acceptably reviewed the notices for generic implications and that appropriate corrective actions were taken, if required, (Closed) Information Notice-87-10: Potential for Water Hammer During Restart of Resid0al Heat Removal pumps. The licensee has ,

reviewed this IN and determined that it is not applicable to LACBWR !

since there is no suppression pool and no other water hammer problems are expecte (Closed) Information Notice 87-12: -Potential Problem with Metal Clad Circuit Breakers, General ~ Electric Type AFK-2-25. The licensee's raview indicated that LACBWR has two of these type breakers. plans were being nade to send one in for a factory overhaul with overhaul of the second pending the results of the first overhau (Closed) Infctmation Notice 87-08: Degraded Motor Leads in Limitorque DC Motor Operators. "The licensee's review shows only one Dl' operated valve, the Alternate Cere Spray Valve Motor, which was instelled prior to 1968; therefore, this IN does not apply to LACBW .

_ _ _ - _ __ _ _

,

.

.

4 Organization and Administration The inspector verified that changes in the organizational structure had been reported to the NRC.through the licensee's QA program submitted

, October 30, 1986 and verified that persons assigned to new or different'

positions in the licensee's. organization 'since ,the last inspection of.this area satisfy qualifications identified in the technical specifications, the licensee's QA program, and applicable' national standard . Transportation On April 428, 1987, the inspector' observed the loading of a dried resin container into a shipping cask;.however, the two meter readings from the lateral outer edges of the vehicle slightly exceeded the 10 MREM /HR DOT shipping limit and the liner. was placed back into the waste building cubical to await decay or resin. rearrangement to lower the dose rat . Open Items Open items'are matters which have been discussed with the licensee, which will be reviewed further by the inspector, and which involve some action on the part of the NRC or licensee or bot . Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1)

throughout the inspection period and at the conclusion of the inspection and summarized the scope and findings of the-inspection activities. The licensee acknowledged the findings as reported larein and Jid not identify such documents.or processes as proprietar l l

_-_-_- .. ..