IR 05000285/1987033

Insp Rept 50-285/87-33 on 871201-31.No Violations or Deviations Noted.Major Areas Inspected:Followup on Previously Identified Items,Ler Followup,Operational Safety Verification & Plant Tours

ML20148R929
Person / Time
Site:	Fort Calhoun
Issue date:	01/27/1988
From:	Harrell P, Reis T, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20148R893	List: IR 05000285/1987033
References
50-285-87-33, NUDOCS 8802020305
Download: ML20148R929 (22)

Text

e S APPENDIX U. S. NUCLEAR REGULATORY COMMISSION

REGION IV

NRC Inspection Report: 50-285/87-33 Docket: 50-285 Licensee: Omaha Public Power District 1623 Harney Street Omaha, Nebraska 68102 Facility Name: Fort Calhoun Station Inspection At: Fort Calhoun Station, Blair, Nebraska Inspection Conducted: December 1-31, 1987 Inspectors: [h _

l-1-66 P.\H.TarrWSenior Resident Reactor Date NJInspector w /-7 88 T. Reis, Re'siderit Reactor Inspector Date

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Approved- a / O- 3I T. F. WestQr: kin, Chief, Projects Date Section B 8802o20305 gDR ADOCK 05008002[)

PDR

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Inspection Summary Inspection Conducted December 1-31, 1987 (Report 50-285/87-33)

Areas Inspected: Routine, unannounced inspection including followup on previously identified items, licensee event report followup, operational safety verification, plant tours, safety-related systen walkdowns, monthly maintenance observations, monthly surveillance observations, security observations, radiological protection observations, in office review of periodic and special reports, followup on an onsite event, cold weather preparations, and review of the licensee's program for natural circulation cooldown, Results: Within the 13 areas inspected, no violations or deviations were identified,

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DETAILS Persons Contacted

• Andrews, Division Manager, Nuclear Production

• Gates, Plant Manager J. Bailey, Engineer

• C. Brunnert, Supervisor, Operations Quality Assurance M. Burgraff, Engineer

• Core, Supervisor, Maintenance T. Dexter, Supervisor, Security

• Eidem, Manager, Mechanical and Nuclear Engineering

• J. Fisicaro, Supervisor, Nuclear Regulatory and Industry Affairs J. Foley, Supervisor, I&C and Electrical Field Maintenance

• J. Gasper, Manager, Administrative and Training Services

• L. Gundrum, Plant Licensing Engineer

• B. Hansher, Licensing Engineer J. Kecy, Acting Reactor Engineer J. Lechner, Plant Engineer

• T. McIvor, Supervisor, Technical

• K. Morris, Division Manager, Quality Assurance and Regulatory affairs

• T. Patterson, Supervisor, Technical G. Roach, Supervisor, Chemical and Radiation Protection D. Trausch, Supervisor, Operations S. Willrett, SJpervisor, Administrative Services and Security

• Denotes attendance at the monthly exit intervie The inspectors also contacted other plant personnel, including operators, technicians, and administrative personne . Followup on Previously Identified Items (0 pen) Severity Level IV Violation 285/8634-03: Failure to operate the waste gas panel (AI-110) in accordance with the approved procedure This violation involved the failure of the licensee to properly perform a valve alignment when placing AI-110 in the standby mod On three occasions during an inspection performed in December 1986, the valve alignment on AI-110 was found to be incorrec In response to this violation, the licensee committed to take the following actions. The results of the review performed by the NRC inspector has been included in the discussion of each ite . Procedures 01-WDG-3, "Waste Gas Sampling System (AI-110)

Operation" and CMP-2.2, "Waste Gas Sampling System" were revised to provide concise step-by-step instructions for the technicians when operating AI-11 The revision was issued to eliminate the

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requirement for the technician to perform a complete alignment of all system valves after taking a sample. The NRC inspector reviewed Procedures 01-WDG-3 and CMP-2.2 to verify that the changes made by the licensee provided adequate instructions for the operation of AI-110. Based on a review of the procedures, it appeared that the revisions provided adequate and usable instruction . A review of other procedures used by the chemistry group was performed to verify that the instructions provided were adequate. The results of the review concluded that no additional procedure changes were require The NRC inspector, in followup on this item, noted that the procedure review performed by the licensee was not documente In discussions with licensee personnel about the method used for the review, it appeared that the review was performed even though it was not documented. The NRC inspector reviewed selected procedures to establish that the instructions provided were adequat No problems were note . Discussions were held with the chemistry technicians to stress the importance of verbatim compliance during the performance of evolutions prescribed by procedures. Discussions were also provided to stress the proper steps to be taken if, during the performance of a procedure, the evolution could not be completed in accordance with procedural instruction During followup on this item, the NRC inspector again noted that the discussions held with the chemistry technicians were not adhered to. The NRC inspector discussed this item with selected chemistry technicians and determined that each technician was aware of the need for verbatim compliance and the steps to be taken if compliance could not be achieved when performing evolution In response to this violation, the licensee stated that the root cause for this violation was a lack of adequate training. In followup on this element of the licensee's response, it was determincd that the licensee had provided additional training for only one of the six chemistry technicians. The nonlicensed training group prepared a lecture; however, only one technician attended the class. In discussions with licensee personnel, it was discovered that management of the chemistry department did not make the technicians available to attend the prepared lectur This item remains open pending action by the licensee to provide training to chemistry technicians in the operation of AI-11 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ __ __ _ _ _ _ _ _

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b. (0 pen) Severity Level IV Violation 285/8702-03: Failure to maintain the procedure for alignment of the breakers on the 480-volt motor control centers (MCC) in an up-to-date conditio This violation was related to the licensee's failure to maintain the procedure used for alignment of the breakers on the 480-volt MCCs in an up-to-date condition. In response to this violation, the licensee revised and reissued Checklist E of Procedure OI-EE-2, "480-Volt System (Normal Operation)," in May 1987 to correct the discrepancies noted during the walkdown performed by the NRC inspector in January 198 During the July through August 1987 inspection, the NRC inspector performed a walkdown of the 480-volt electrical system using the

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revised checklist. As documented in NRC Inspection Report 50-285/87-20, this violation remained open pending the issuance of another revision to Checklist E. The revision issued in May 1987 still contained deficiencies identified in January 1987 that had not been correcte The licensee issued another revision to Procedure 01-EE-2 on November 198 This revision incorporated Checklists B, C, D, and E of Procedure 01-EE-2 into a single comprehensive checklist, designated as Checklist B. The NRC inspector reviewed the revised Checklist B in conjunction with Figure 8.1-1 of the Updated Safety Analysis Report (USAR) and perfomed walkdowns of various MCC The NRC inspector found that the revised checklist still did not provide adequate instructions for all the electrical breakers on the MCC The NRC inspector noted that some safety-related loads were not included on the checklist and there was no overall defined scope as to what should be included on the checklist for normal operation of the 480 volt syste This item remains open pendir.g the final issuance of a revision to Checklist B that includes instructions for the positioning of all safety-related breakers on the 480-volt MCCs and that accurately reflects the existing loads served by the various MCC c. (Closed) Severity Level V Violation 285/8710-01: A firewatch was not established for a nonfunctional fire barrier in accordance with Technical Specification (TS) requirement This item was related to the failure of the licensee to establish a firewatch for the emergency diesel generator room doors and for a fire damper installed between the diesel generator rooms. Hoses were run through the doors and damper causing the fire barriers to be nonfunctiona To ensure that fire watches are established as required by the TS, the licensee revised Procedure 50-0-38, "Firewatch Duties and Turnover Procedures," to require notification of the shift supervisor and/or security personnel when a fire barrier is inoperable. Upon

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notification, a fire watch will be establishe The licensee revised Procedure SCP-14, "Patrol Procedures," to require security guards to i monitor for nonfunctional fire barriers during their hourly tours through the plant. If a nonfunctional fire barrier is identified, the shift supervisor is notified so that a fire watch can be established. In addition to revising the above procedures, the licensee also revised Forms FC-37, "Daily Fire Door Log," and FC-1006, "Hourly Fire-watch Patrol Log." The forms were revised to record the name of the firewatch assigned to provide assurance that the individual has been appropriately trained and that the individual had not been assigned other duties that would detract from firewatch dutie The NRC inspector reviewed the actions taken by the licensee, as discussed above. Based on this review, it appeared that the licensee had taken the appropriate actions to ensure that firewatches would be provided when fire barriers became nonfunctiona (Closed) Severity Level IV Violation 285/8715-02: Unauthorized modification of a safety related syste This violation was related to the unauthorized installation of tubing and a gage in the containment sump discharge line. The tubing and gage were installed during the 1987 refueling outage and the licensee could not provide documentation to indicate that the modification was performed in accordance with approved instructions. The installation of the gage could not be traced, by the licensee, to any authorized modification, surveillance test, or calibration procedure. The gage

. and tubing were removed immediately upon notification by the NRC inspecto At the time of the notification of the problem by the NRC inspector, the licensee conducted a review to determine which onsite group may have installed the tubing and gage. After the review, licensee personnel could not determine which group had installed the gage and tubing. The licensee determined that the gage was not of the type and manufacturer normally used by plant personne To prevent recurrence of this problem, the licensee issued a memo to all personnel with unescorted access to the site. The memo discussed the details of this violation and reminded all personnel that system modifications can only be made when allowed by approved documentatio In addition, the licensee has also included a discussion of this violation in the general employee training prograft to ensure new employees and contractor personnel are made aware of the cause of this violatio The NRC inspector reviewed the actions taken by the licensee in response to this violation. The NRC inspector monitored the licensee's activities related to determining the origin of the tubing and gage, at the time the problem was identified, and noted that

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adequate followup activities were performed. The NRC inspector verified that each individual had acknowledged the receipt of the memo issued by the licensee that provided information regarding this violation. Based on the review performed and the circumstances related to this violation, it appeared that the licensee took appropriate actions to correct the problem and to prevent recurrenc (Closed) Open Item 285/8729-02: An anomaly was noted during the performance of surveillance testing on the pressurizer level signa This open item was related to the actuation of the control board annunciator for emergency feedwater storage tank (EFWST) low-level alarm during performance of the surveillance test, Procedure ST-PL-1, for verifying the accuracy of the pressurizer level signal. At the time of the performance of ST-PL-1, no reason could be established as to why the EFWST low-level alarm was actuate The NRC inspector observed the performance of all steps of Procedure ST-PL-1 and noted no similar anomalies. However, during performance of the te,t, the licensee noted that the strip chart recorder for one channel of pressurizer level did not function properly. The licensee issued Maintenance Order (MO) 875796 for repair of the recorde Repairs were completed shortly after completion of the surveillance test. In discussions with licensee personnel, it was established that during performance of Procedure ST-PL-1 in November 1987, the level of the EFWST was close to the alarm setpoint. Licensee personnel stated that during performance of Procedure ST-PL-1, slight voltage fluctuations occurred in the annunciator supply voltage which, in turn, caused actuation of the EFWST low-level alarm since the actual level was nea' the set poin Since no anomalies occurred during performance of Procedure ST-PL-1, this item is considered closed. The NRC inspectors will observe the performance of this surveillance test during future routine surveillance observation activitie . Licensee Event Report (LER) Followup Through direct observation, discussions with licensee personnel, and review of selected records, the following event reports were reviewed to determine that reportability requirements were fulfilled, immediate corrective action was accomplished, and corrective action to prevent recurrence had been accomplished in accordance with T The LERs listed below are closed:

87-019 Inoperability of fire water system 87-022 Defects in the emergency feedwater storage tank

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. .87-028 Failure to submit a special report in accordance with TS 2.19(7)

A discussion of the review of each LER is provided below: LER 87-019 reported an event where, due to personnel error, the diesel-driven fire pump (FP-1B) was improperly returned to service resulting in one fire pump being inoperable in excess of 7 days and both fire pumps being inoperable for approximately 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />. This LER was issued by the licensee as a special report as required by TS 2.19(4) An operator started and ran FP-1B to prove operability following maintenance activities. Prior to the test, the operator shut the discharge valve on FP-1B, as required by Procedure 01-FP-6, "Diesel Pump Fire Test." Upon completion of the test, the operator incorrectly assumed that other maintenance activities were in progress and left the FP-1B discharge valve shut, causing the pump to be inoperable since the pump was isolated from the fire water syste Approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> later, the electric-driven fire pump (FP-1A)

was removed from service for maintenanc Removal of FP-1A from service caused the fire water system to be inoperable since neither fire pump was availabl During a plant tour made approximately 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> after removing FP-1A from service, an operator noted that the FP-1B discharge valve was shut, causing both fire pumps to be out to servic The valve was immediately opene The cause of this event was due to the incorrect assumption made by the operator that further maintenance would be performed on FP-1 In addition, the operator failed to notify the shift supervisor that the FP-1B discharge valve was lef t in the shut position. To prevent further events of this type, the licensee revised and reissued Procedure OI-FP-1, "Fire Protection System-Normal Conditions," to require a shift supervisor signoff for all fire system valve alignment The signoff will ensure that the shift supervisor will be aware of the status of fire system valves. The licensee also

, provided training to the appropriate individuals to make the individuals aware of the root causes of this even The NRC inspector reviewed the revision issued to Proceduru 01-FP-1 to verify that the shift supervisor signature had been included, and reviewed the completed documentation of fire pump testing since the event occurred. No problems were noted. The NRC inspector also performed a review to verify that the event described by this LER had been discussed with operations personnel. This review was performed by discussing the event with selected operations personnel. In each case, the operators were knowledgeable of the event and the causes of

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the event. Based on the reviews performed by the NRC inspector, it appeared that the licensee had taken appropriate actions to preclude recurrence of this event, b. LER 87-022 reported defects that were discovered in the EFWST during the 1987 refueling outage. The defects identified were surface cracking, slag inclusions, and lack of fusion in welds. The licensee identified the probable causes of the defects to be the use of welding rod without preheat resulting in shrinkage, improper cleaning of copper deposits causing a lack of fusion, and poor workmanshi The licensee repaired the defects, hydrostatically tested the tank, and returned the tank to servic An NRC inspector performed an onsite review of licensee activities that were taken to correct the defects in the EFWST. The details of the review are provided in NRC Inspection Report 50-285/87-14. Based on this review, this LER is considered closed, c. LER 87-028 described an event where the licensee failed to submit a special report to the NRC in accordance with the requirements of TS 2.19(7). The TS requires that a report be submitted within 30 days from the day a TS fire barrier is determined to be '

nonfunctional for greater than 7 days. On March 19, 1987, the fire barrier separating Fire Areas 41 and 42 was rendered inoperable. The licensee failed to submit the special report because the report was lost during the licensee's internal review process. The special report was discovered on October 8, 1987. In discussions with ;

licensee personnel, the NRC inspector determined that the licensee intended to submit the special report to the NRC as a part of this LER; however, the licensee did not correctly complete the LER form to indicate that the LER contained information related to a special l repor On December 31, 1987, the licensee issued a revision to this

! LER to include the proper notations.

i l To ensure that all special reports are submitted to the NRC in a I timely manner, the licensee revised Procedure 50-R-4, "Station

! Incident Reports," to establish a program for initiation of a station

! incident report (SIR) in each case where a special report is required l to be submitted to the NRC. Initiation of a SIR will provide an

! internal tracking system that will ensure all special reports are issued in accordance with the time limits specified in the T The NRC inspector reviewed Procedure 50-R-4 to verify that the licensee had established a program to ensure the special reports l required by the 15 were issued in a timely manner. Based on the review, it appeared that the licensee had established an acceptable program. The NRC inspector reviewed a selection of other events where a special report was required to be submitted to the NRC. No problems were noted.

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'10 The;NRC inspector also reviewed the repairs made to the fire barrier between Fire Areas'41 and 42 to verify that the fire barrier was

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returned to a functional status and that an hourly fire' watch had been~ established. The fire barrier was repaired in accordance.with

. instructions provided in MO 87124 No problems were noted during this revie No violations or deviations were' identifie . Operational Safety Verification The NRC inspectors conducted reviews and observations of selected activities to verify that facility operations were performed in conformance with the requirements established under 10 CFR,. administrative

. procedures, and the TS. The NRC inspectors made several control room observations to ' verify the following:

. Proper shift staffing

. Operator adherence to approved procedures and TS requirements

. Operability of reactor protective system and engineered safeguards equipment

. Logs, records, recorder traces, annunciators, panel indications, and switch positions complied with the appropriate requirements

. Proper return to service of components

. M0s initiated for equipment in need of maintenance

. Appropriate conduct of control room and other licensed operators

. Management personnel toured the control room on a regular basis The following items were identified during control room observations, During tours of the control room, the NRC inspectors noted that an excessive number of plant personnel were in the control room main boundary. The control room main boundary is defined as the area encompassed by the ma 4 control board and other safety-related control panel On December 29, 1987, the NRC inspector noted that 8 people were in the control room main boundary, and again on December 30, 1987, the NRC inspector noted 15 people in the control room main boundary, in addition to the normal control room staff. With this number of additional personnel in the area, it caused an excessive noise level-and distraction to the control room operator !

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The NRC inspector discussed the situation with the.onshift operators from four of the six shifts. Based on these discussions, the NRC inspector noted that the operators felt that they did not have management's support in requesting personnel to leave.the control room. Operations personnel related that on a number of occasions in the past, they had requested that personnel leave the control room and the personnel departed. Operations personnel stated that shortly thereafter, management personnel visited the control room and expressed dissatisfaction with operations personnel requesting that personnel leave the control room. For this reason, operations personnel have been hesitant towards clearing the control room of unnecessary personne The NRC inspector discussed the concern of excessive personnel in the control room with licensee management. Licensee management stated that a review would be performed and controls developed to ensure that unnecessary personnel are kept out of the control room main boundar This item will remain open pending the establishment of a program by licensee management for limiting personnel access to the control room and a review of the program by the NRC inspector (285/8733-01),

b. On December 18, 1987, the NRC inspector was in the control room at lunch time when operations personnel were attempting to contact the shift chemistry technician for assistance. ' The control room operators were unable to contact the technician after paging the technician eight times over the public address system. The page was eventually answered by a chemistry technician that was not assigned onshift duties.

l In discussions with onshift operations personnel, the NRC inspector determined that the shift chemistry technician routinely does not answer pages during the lunch period, not only on day shift, but also on other shifts. Operations personnel also stated that the health physics technicians do not routinely answer pages during lunch period The NRC inspector discussed the event described above with licensee management to stress the need to develop team work among the various groups with the plant organizations. Licensee management stated that a review would be performed to determine the reasons for technicians not answering pages. This item remains open pending a review by licensee management and a followup review by the NRC inspector of the licensee's actions (285/8733-02).

c. On December 30, 1987, the NRC inspector noted that Charging Pump B (CH-1B) was out of service. Although CH-1B did not cause the plant to be in a TS limiting condition for operation, the NRC inspector became concerned with the adequacy of Procedure A0P-6,

"Emergency Fire Procedure." Procedure A0P-6 provides instructions

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for the operation of equipment from the. alternate-shutdown-panel in the event the control room must be evacuated due to a fir Procedure A0P-6 provides instr'Jctions for maintaining the plant in a hot-shutdown condition using CH-1B. No instructions have been provided for maintaining the plant in hot shutdown if CH-1B is not available, as was the case on December 30, 198 The NRC inspector discussed the situation with various onshif t operators. In each case, the operators were aware of the actions l required for operation of one of the other two charging pumps, in the i event CH-1B was inoperable. However, the operators were not aware of I the details for pump operation such as which individual was ;

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supply breake I The NRC inspector discussed the adequacy of Procedure A0P-6 with management personnel. Management personnel stated a review would be performed to determine the adequacy of Procedure A0P-6 and then discuss the results with the NRC inspector. Licensee management did not complete the review prior to the end of this inspection perio This item remains unresolved pending the review of Procedure A0P-6 by licensee management-and a discussion of the results (285/8733-03).

No violations or deviations were identifie . Plant Tours The NRC inspectors conducted plant tours at various times to assess plant and equipment conditions. The following items were observed during the tours:

. General plant conditions, including operability of standby equipment, were satisfactor . Equipment was being maintained in proper condition, without fluid leaks and excessive vibratio . Plant housekeeping and cleanliness practices were observed, including no fire hazards and the control of combustible materia . Performance of work activities was in accordance with approved procedures.

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. Portable gas cylinders were properly stored to prevent possible missile hazard . Tag out of equipment was performed properly.

I f . Management personnel toured the operating spaces on a regular basi . The auxiliary feedwater pumps were not steam boun _

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During a tour of the plant on November 30, 1987, the day after performance of the monthly surveillance test, the NRC inspector noted a 3/8-inch layer of.a substance floating on.the water in the cooling water surge tank sightglass of Emergency Diesel Generator (EDG) 2. Tlie substance appeared to be lubricating oi The NRC inspector notified the licensee of the layer in the expansion tank. The NRC inspector's concern was that the presence of oil in the water system was a precursor to the potentia failure of the cooling water / lubricating oil coole The concern was based on an event that occurred on September 23, 1987, where EDG 2 tripped off during surveillance testing due to high temperatures in the cooling water system, and the overheating event may have damaged internal components on EDG The licensee collected a sample of the water in the EDG 2 sightglass and sent it offsite for analysis. On December 4, 1987, the licensee was notified that the sample contained lubricating oi On December 8, 1987, the licensee contacted the EDG vendor (EMD) to obtain EMD's evaluation of the cause for the presence of oil in the sightglas EMD stated that a cmall amount of oil in the sightglass was not unusual because the engine gaskets are coated with lubricating oil prior to assembly of component The licensee performed an engine disassembly in May 198 EMD recommended that the licensee check for the presence of water in the lubricating oil system. EMD's concern was that water may have entered the lubricating oil sp tem because the pressure in the water system is greater than the pressure in the oil system when the EDG is in a standby status, the normal operating mode of the ED The presence of water in the luhricating oil would confirm that a cooling water / lubricating oil cooler leak _ existed. EMD recommended that the licensee inspect the engine upper' deck for sludge buildup and check the lubricating oil sump for water. The licensee performed the inspections, in accordance with MO 875627, and no water was foun On December 24, 1987, the day after performance of the monthly surveillance test on EDG 2, the NRC inspector again noted that the cocling water surge tank sightglass contained a 2-inch layer.of lubricating oi The NRC inspector notified the licensee of the presence of'the oil. The licensee took a sample of the water from the sightglass and transported it offsite for analysi The analysis was not completed prior to the end of this inspection perio On December 31, 1987, the licensee again contacted EM During the discussion, EMD stated that if the engine had been overheated, seals will leak and pass a small amount of oil into the cooling water system. During operation of the EDG under load, oil pressure is greater than cooling water pressure, causing oil to leak into the wate The oil will locate in the high points of the system and will be transported to the cooling water surge tank as the engine is subsequently operated under loa During the ongoing evaluation performed by the licensee to determine if a potential problem with EDG 2 existed, at no time did the licensee consider EDG 2 to be inoperable. The licensee stated that even though a potential problem existed with EDG 2, there was no evidence to indicate that EDG 2

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.could not perform its intended cafet'y function. -The NRC inspector reviewed the actions taken by the licensee and concurred that no evidence existed that would indicate EDG 2 is inoperabl At the end of this inspection period, the licensee was continuing to evaluate-the potential problem with EDG 2. The licensee planned to obtain the services of a vendor technical representative to perform an onsite observation of the operation of EDG 2 to evaluate the identified potential problem. This item remains open pending the completion of the evaluation

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No violations'or deviations were identifie . Safety-Related System Walkdowns The NRC inspectors walked down accessible portions of the following safety-related systems to verify system operability. Operability was determined by verification of selected valve and switch position The systems were walked down using the drawings and procedures note . Engineered safeguards controls (Procedure 01-ES-1, Checklist A, Revision 18)

. High pressure safety injection system (Procedure 01-SI-1, Checklist A, Revision 40 and Drawing 23866-210-130, Revision 43)

. Low pressure safety injection system (Procedure OI-SI-1, Checklist B, Revision 40 and Drawing 23866-210-130, Revision 43)

. 480-volt electrical distribution system (Procedure 01-EE-2, Checklist 8, Revision 13 and USAR Figure 8.1-1, Revision 32)

During walkdown of the 480-volt electrical distribution system, several discrepancies were noted and are detailed in paragraph 2.b of this inspection repor During walkdown of the other three systems listed above, the NRC inspectors noted no oiscrepancies between the drawings, procedures, and plant as-built conditions for the selected areas checke No violations or deviations were identifie . Monthly Maintenance Observations The NRC inspectors reviewed and/or observed selected station maintenance activities on safety-related systems and components to verify the maintenance was conducted in accordance with approved procedures, regulatory requirements, and the TS. The folicwing items were considered during the reviews and/or observations:

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. The TS 1imiting conditions for operation were met while systems or components were removed from servic . Approvals-were obtained prior to initiating the wor . Activities were accomplished using approved M0s and were inspected, as applicabl . Functional testing and/or calibrations were performed prior to returning components or systems to servic . Quality control records were maintaine . Activities were accomplished by qualified personne . Parts and materials used were properly certifie . Radio 1ogical and fire prevention controls were implemente The NRC inspectors reviewed and/or bserved the following maintenance activities:

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. Repair of leakage for Valves PCV-742A and PCV-7428 at containment Penetration M-87 (M0 877042)

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. Repair of pressurizer level chart recorder (M0 875796)

. Repair of steam generator level transmitter (M0 871556)

. Repair of a fire detector (M0 874448)

. Flushing of EDG 2 cooling water surge tank (M0 875886)

. Checking of the EDG 2 lubricating oil system for water (M0 875627)

No violations or deviations were identifie . Monthly Surveillance Observations The NRC inspectors observed selected portions of the performance of and/or reviewed completed documentation for the TS-required surveillance testing on safety-related systems and components. The NRC inspectors verified the following items during the testing:

. Testing was performed by qualified personnel using approved procedure . Test instrumentation was calibrate . The TS limiting conditions for operation were me . - ._ _ _ . _ ._

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. Removal and restoration of-the affected system and/or component were accomplishe . Test results conformed with TS and procedure requirement . . Test results were reviewed by personnel other than the individual directing the tes . Deficiencies identified during the testing were properly reviewed and resolved by appropriate management personne '

The NRC inspectors observed and/or reviewed the-documentation for the following surveillance test activitie The procedures used for the test activities are noted in parenthesi . Leak rate testing of containment isolation Valves PCV-742A an PCV-7428 (ST-CONT-3)

. Monthly testing of EDG 1 (ST-ESF-6)

. Monthly calibration of pressurizer level (ST-PL-1)

. Auxiliary feedwater pump and remotely operated valve check (ST-FW-1) ,

. Auxiliary feedwater valve inservice testing (ST-ISI-FW-1)

. Ventilating air valves inservice testing (ST-ISI-VA-1)

. Stroke testing of safety-related valves not in the inservice inspection program (SP.-STR0KE-1)

. Monthly test of the station batteries (ST-DC-1)

! . Monthly test of EDG 2 (ST-ESF-6)

On November 30, 1987, the licensee performed Procedure ST-CONT-3 to determine the leakage through containment purge Valves PCV-742A and PCV-742 Both of these valves are containment isolation valves. The test was performed as a routinely scheduled. test in accordance with the TS. When the test was performed, the licensee determined that the leakage rate was 260,000 standard cubic centimeters per minute (sccm). The acceptance criteria for leakage rate is 18,000 secm. Based on the results of the testing, the licensee entered the limiting condition for operation

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of TS 3.5(4)c. The TS requires that a plant shutdown be initiated if repairs are not completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. The licensee notified the NRC resident inspector and NRC Operations Center of the problem within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> as required by 10 CFR Part S0.72. The licensee initiated repairs in accordance with M0'877042. The valve operator for Valve PCV-742B was adjusted to ensure that the valve disk was firmly seated against the valve seat. The leak rate test was reperformed and the leakage was determined to be 0 sccm. The licensee completed the valve repairs within the 48-hour

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time limit specified in TS 3.5(4) On December 1, 1987, the NRC inspector observed the test and verified that the data obtained was accurat On December 30, 1987, the licensee submitted LER 87-038 to provide details of this event and to provide a corrective action program to correct this problem. The NRC inspectors will review the corrective action program during close out of LER 87-03 No violations or deviations were identifie . Security Observations The NRC inspectors verified the physical security plan was being implemented by selected observation of the following items:

. The security organization was properly manne .- Personnel within the protected area (PA) displayed their identification badge . Vehicles were properly authorized, searched, and escorted or controlled within the P . Persons and packages were properly cleared and checked before entry into the PA was permitte . The effectiveness of the security program was maintained when security equipment failure or impairment required compensatory measures to be employe . _The PA barrier was maintained and the isolation zone kept free of transient materia . The vital area barriers were maintained and not compromised by breaches or weaknesse . Illumination in the PA was adequate to observe the appropriate areas at night.

. Security monitors at the secondary and central alarm stations were

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functioning properly for assessment of possible intrusion No violations or deviations were identified.

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10. Radiological Protection Observations

, The NRC inspectors verified that selected activities of the licensee's

! radiological protection program were implemented in conformance with the facility policies and procedures and in compliance with regulatory requirement The activities listed below were observed and/or reviewed:

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. Health physics ~(HP) supervisory personnel canducted plant tours to check on activities in progres . Radiation work permits contained the appropriate information to ensure work was performed in a safe and controlled manne . Personnel in radiation controlled areas (RCA) were wearing the required personnel monitoring equipment and protective clothin . Radiation and/or contaminated areas were properly posted and controlled based on the activity levels within the are . Personnel properly frisked prior to exiting an RCA.-

No violations or deviations were identifie . in-office Review of Periodic and Special-Reports In-office review of periodic and special reports was performed by the NR resident inspectors and/or the Fort Calhoun project engineer to verify the following, as appropriate:

. Reports included the information required by appropriate NRC requirement . Test results and supporting infnrmation were consistent with design predictions and specification . Determination that planned corrective actions were adequate for resolution of identified problem . Determination as to whether any information contained in the report

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should be classified as an abnormal occurrenc The NRC. inspectors reviewed the'following:

. Enforcement discretion for the containment isolation purge valves, dated December 1, 1987

. Followup and withdrawal of enforcement discretion request of December 1, 1987, dated December 2, 1987

. Monthly operations report for November 1987, undated i

. November monthly operating report, dated December 14, 1987 During review of reports, NRC personnel identified 10 CFR Part 21 reports submitted by suppliers or vendors that appeared to be applicable to the licensee's facilit The NRC resident inspector provided copies of these reports to the plant licensing engineer for review of applicability by the licensee. The reports provided are listed below:

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. .A letter dated October 23, 1987, from the Public Service Electric and Gas Company'related to defects in the containment hydrogen analyzer . A letter dated October 19, 1987, from the Philadelphia Electric Company related to nondestructive examination services provided by-the Eastern Testing and Inspection Compan . A letter dated October 16, 1987, from the Westinghouse Electric Corporation related to defects in Type W-2 cell switche . A' letter dated' September 29, 1987, from the Morrison-Knudsen Company related to a potential problem with saturable core transformers installed in emergency diesel generator . A letter dated November'12, 1987, from General Electric related to insufficient latch engagement in HFA relay . A letter. dated October 2, 1987, from Combustion Engineering related to' fasteners installed in motor-operated valves supplied by Borg-Warne No violations or deviations were identifie . Followup on an Onsite Event On July 6, 1987, the licensee experienced an event where water was introduced into the instrument air system. On September 23, 1987, EDG 2 was automatically shut down during a surveillance test due to the exhaust damper failing to open causing high temperatures in the cooling water system. The details of the event are provided in NRC Inspection Report 50-285/87-2 In followup to this event, the licensee identified and removed all

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identified instrument air / water interfaces. In subsequent followup during December 1987, the licensee identified additional instrument air / water interfaces that provided the potential for water to enter the instrument air system. The interfaces consisted of air-operated, pinch-type, and diaphragm-operated valves where failure of a rubber valve component could allow water to enter the air syste At the end of this inspection period, the licensee was in the process of determining the possibility of water entering the air system through the failure of valve internals and establishing a corrective action program, if required. This item remains open pending the completion of the licensee's evaluation and a review of the licensee's conclusions by the NRC inspectors (285/8733-05).

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No violations or deviations were identifie .

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13. Cold Haather Preparations

The NRC-inspectors toured various plant areas and reviewed documentation to verify that the licensee had taken measures to ensure that systems affected by extreme cold weather were properly protected. The items observed and/or reviewed by the NRC inspectors are listed belo . The freezing point of the cooling systems for the plant emergency, security, and technical support center (TSC) diesels had been tested and actions taken, if appropriat . .The steam supply to the condensate storage tank had been initiate . Fire water system piping had been recovered with earth following modifications to the syste . The stop log used to divert the plant. cooling water outflow from downstream to upstream of the intake structure was installed. The flow is diverted to prevent ice' floes from clogging the intake structure grid During review of the above items,.the NRC inspector noted that the licensee had not determined the freezing point of the cooling water system for the security and TSC diesels. The other items were found to be satisfactory. A review by the licensee revealed that documentation had not been issued to require testing of the cooling system freezing poin The licensee stated that the freezing point for both diesels would be checked and documentation would be generated.to perform a routinely scheduled check in the future. This item remains unresolved pending the completion of the freeze point checks, issuance of a procedure for checking the freeze point in the future, and a review of these licensee actions by the NRC inspector (285/8733-06).

No violations or deviation were identifie . Review of the Licensee's Program for Natural Circulation Cooldown The NRC inspector performed a review to verify that the licensee's program for natural circulation cooldown complied with the requirements stated in Generic Letter (GL) 81-21, "Natural Circulation Cooldown," issued on May 5, 1981, the licensee's response to GL 81-21, dated November 13, 1981, and the safety evaluation report (SER) issued by the NRC on October 28, 1983. The NRC inspector reviewed the following item . Commitments stated in the licensee's response to GL 81-21 were adequately incorporated into Procedures 01-RC-11, "Reactor Coolant System Natural Circulation Cooldown", Section HR-2 of E0P-20, "RCS and Core Heat Removal", and E0P-02, "Electrical Emergency."

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. Classroom and simulator training was provided to all licensed operators and shift. technical assistantsJusing the procedure listed abov The results of the reviews performed by the NRC inspector are discussed ~

below:

. It appeared, based-on the review of Procedures 01-RC-11, E0P 20, and E0P-02, that the licensee had adequately implemented.the technical requirements stated in the SER. However, the NRC inspector did note eight examples of where the presentation of the information in the procedures was vague and confusing. It appeared that the information would not have prevented operations personnel from establishing and maintaining natural circulation cooldown. The eight examples were provided to the licensee. The licensee stated that a review of the comments would be performed and revisions issued to the procedures, as appropriate. . This item remains open pending a review by the NRC inspector of the procedure revisions made by the licensee'

(285/8733-07).

. Documentation of classroom lectures and simulator worksheets was reviewed and discussions with licensed operators were performed to verify that training had been provided for natural circulation cooldow Based on these reviews, it appeared that training had been given the licensed operators and shift technical advisors. During discussions with licensed. operators, specific questions were asked regarding the actions necessary to establish and maintain natural circulation cooldown. In each case, the operators demonstrat';.' an indepth understanding of the natural circulation cooldown p w 4 A No violations or deviatians were identifie . Unresolved Items An unresolved item is a matter about which more information is required in order to determine whether it is acceptable, a violation, or a deviatio Two unresolved items are discussed in this inspection repor Item Paragraph Subject 285/8733-03 Review of the adequacy of A0P-6 285/8733-06 13 Determination of the cooling water system freezing points for the security and TSC diesels

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16. Exit Interview The NRC inspector met with you and other members of the licensee staff at the end of this inspection. At this meeting, the NRC inspector summarized the scope of the inspection and the findings.