ML20138M740

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Insp Repts 50-369/85-30 & 50-370/85-32 on 850821-0920. Violations Noted:Two Trains of Pressurizer Heaters W/Backup Emergency Power Inoperable for Period Longer than Allowed by Tech Specs & Failure to Follow Procedures
ML20138M740
Person / Time
Site: Mcguire, McGuire  Duke Energy icon.png
Issue date: 10/18/1985
From: Dance H, William Orders, Pierson R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20138M724 List:
References
50-369-85-30, 50-370-85-32, NUDOCS 8511040270
Download: ML20138M740 (8)
v • d • e


See also: IR 05000369/1985030

Text

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                                        NUCLEAR REGULATORY COMMISSION
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    Report Nos.           50-369/85-30 and 50-370/85-32
    Licensee: Duke Power Company
                    422 South Church Street
                    Charlotte, NC 28242
    Facility Name: McGuire Nuclear Station
   Docket Nos.            50-369 and 50-370                           License Nos.  NPF-9 and NPF-17
    Inspection Conducted:             gust 21 - September 20, 1985
    Inspectors:_               . A
                      W. Orcers, .    ior
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   Approved by:               \      A-                                             /c//8 7
                        Hugh C. Dande, Section Chief                                Dde   igned
                        Division of Reactor Projects
                                                       SUMMARY
   Scope: This routine unannounced inspection involved 328 inspection hours on site
    in the areas of operations, safety verification, surveillance testing and
   maintenance activities.
   Results: Of the areas inspected two violations were identified in the area of
    facility operations and one deviation in the area of surveillance testing.
              8511040270 851021
              PDR         ADOCK 05000369
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REPORT DETAILS
        1.  Persons Contacted

l Licensee Employees 4 

           *T. McConnell, Plant Manager

i *B. Travis, Superintendent of Operations j *D. Rains, Superintendent of Maintenance - 

           *B. Hamilton, Superintendent of Technical Services
 1         *L. Weaver, Superintendent of Administration

j *M. Sample, Superintendent of Integrated Scheduling 

           *E. McCraw, License and Compliance Engineer
           *D. Mendezoff, License and Compliance Engineer
;~         *D. Marquis, Performance Engineer
           *R. White, IAE Engineer
           *R. Branch, Site QA Supervisor
!'          Other licensee employees contacted included construction craftsmen,
!           technicians, operators, mechanics, security force members, and office
 .          personnel.
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           * Attended exit interview.

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        2.  Exit Interview

, i The inspection scope and findings were summarized September 27, 1985, with 

            those persons indicated in paragraph 1 above. The licensee did not identify

l as proprietary any of the materials provided to or reviewed by the , 

            inspectors during this inspection.

I 3. Licensee Action on Previous Enforcement Matters I (Closed) Violation 370/83-55-01. Failure to implement prerequisite 4-6 of 

            Procedure IP/0/A/3010/06 in that red tags were not placed on breakers of the           ;

l decay heat removal system valves, NO-1 and NO-2. Adequate corrective steps 

            have been taken to avoid further violations of this type. This item is
closed.

i ! (Closed) Violation 370/84-04-01. Failure to follow procuedres resulting in ! 

            the destruction of the 2-B NV pump and reactor trip. Adequate corrective

! steps have been taken to avoid further violations of this type. This item I 

            is closed.
            (Closed) Violation 369/84-10-01. Failure to follow procedure concerning                 ,
            independent verification resulting in the operability of 1-A NV pump for 7              i
            days in violation of Technical Specification Action Statements 3.1.2.2, .
            3.1.2.4 and 3.5.2. Adequate corrective steps have been taken. This item is
            closed.

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    (Closed) Violation 369/84-11-02 and 370/84-09-03. Failure to perform
    required testing of new penetrations leading to violation of containment
    integrity. The licensee has committed to reviewing containment integrity at
    the end of each outage to assure that all completed or uncompleted
    modifications have not adversely affected containment integrity. This
    should eliminate future occurrences of this problem.         These items are
    closed.
 4  Unresolved Items
    An Unresolved Item is a matter about which more information is required to
    determine whether it is acceptable or may involve a violation or deviation.
    One unresolved item was identified during this report period and is
    discussed in paragraph 8.
 5. Plant Operations
    The inspection staff reviewed plant operations during the report period, to
    verify conformance with applicable regulatory requirements. Control room
    logs, shift supervisors logs, shift turnover records and equipment removal
    and restoration records were routinely perused.      Interviews were conducted
    with plant operation,s, maintenance, chemistry,         health physics, and
    performance personnel.
    Activities within the control room were monitored during shifts and at shift
    changes. Actions and/or activities observed were conducted as prescribed in
    applicable station administrative directives.     The complement of licensed
    personnel on each shift met or exceeded the minimum required by technical
    specifications.
    Plant tours taken during the reporting period included but were not limited
    to the turbine buildings, auxiliary building, units 1 and 2 electrical
    equipment rooms, units 1 and 2 cable spreading rooms, and the station yard
    zone inside the protected area.

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    During the plant tours, ongoing activities, housekeeping, security, equip-
    ment status and radiation control practices were observed.

i Unit 1 Operations l 

    McGuire Unit 1 began the reporting period in Mode 1 operating at 100% power.

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    It was maintained in Mode 1 at or about 100% power for the duration of the
    reporting period.
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     Unit 2 Operations
     McGuire Unit 2 began the reporting period in Mode 1 operating at 100*4
     power. It was maintained in Mode 1 at or about 100*; power until August 24
when power was reduced to 10*4 and the turbine was taken off line to
,    facilitate vibration analysis on the main generator.                   Following this

, analysis the main generator was paralleled to the grid at 1:50 a.m. on 

     August 26, 1985. Power was subsequently increased and the unit was
     maintained at or about 100*s power for the duration of the reporting period.
6. Battery Charger EVCS
!    On July 23, 1985, station personnel determined that the operability
     surveillance test had not been performed on the station standby battery
     charger EVCS in the required time frame. The standby charger can be aligned
     to supply vital loads when one of the four normal vita chargers is out of
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     service. On August 13, 1985, it was found that the standby charger had been
     placed in service at least twice supplying vital loads. These two instances
     occurred during the period of July 1 thru July 15, 1985.
     The four normal vital chargers have been out of service for maintenance or

, testing approximately 26 other tines during the period after the surveil- i lance had expired. It cannot be readily determined how many additional 

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     times EVCS was placed in service during the performance of these tests.
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     The first surveillance test for EVCS was completed on July 9,1982. On
     May 27,1984 the 18 month surveillance interval plus the 4.5 month grace
     period had expired for the EVCS standby charger.

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     Technical Specification 4.8.2.1.2 does not specifically identify the standby
     charger surveillance testing requirements.                  Further, the Technical
     Specification Reference Manual did not address the standby charger. These
     documents were used to establish the equipment requiring periodic

, operational testing at the beginning of the PM/PT program. Resultantly, the 

     program did not include this test.

, l A preventive maintenance (PM) schedule was established on EVCS in 1981.

This PM involves a generic inspection for cleanliness, physical damage,
     etc., and also during recent tests has included an output voltage check to
provide a functional verification of the charger operation. This PM is

j performed.every three months but does not satisfy the output current test l requirements stated in the Technical Specifications. i

In as much as this violation meets the criteria discussed in 10CFR Part 2

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     Appendix C, in that it was licensee identified, was a Severity Level IV
     violation, was reported and corrected and could not reasonably be expected                            I
     to have been prevented, a notice of violation will not be issued.

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   7. Technical Specification Violation
      On September 11, 1985 at 9:10 a.m. the 1A Diesel Generator was taken out of
      service during the performance of PT/1/A/4350/15A, Diesel Generator 1A
      Periodic Test. Later that morning at 9:50 a.m. the supply breaker to the B
      pressurizer heaters tripped open. When this occurred the unit entered the
      action statement of Technical Specification 3.8.1.1 which in summary says
      that all required systems, subsystems, trains, components, and devices that
      cepend on tne remaining operable diesel generator as a source of emergency
      power must also be operable and further states that if these conditions are
      not satisfied within 2 hours the unit must be in at least hot standby within

, the next 6 hours and cold shutdown within the following 30 hours. In as 

      much as the operators had overlooked the consequences of the B pressurizer
      heaters tripping, no action was taken.
      Technical Specification 3.4.3 requires for a pressurizer to be operable that
      at least two groups of pressurizer heaters be operable, each having a
      capacity of at least 150 KW. The action statement requires that the unit be
      in at least hot standby with the reactor trip breakers open within 6 hours
      and in hot shutdown within the following 6 hours with the pressurizer
      inoperable. Since the B pressurizer heaters were tripped open and the A
      pressurizer heaters emergency power supply was not available, two groups of
      pressurizer breakers were not available and the pressurizer was inoperable.
      The 1 A diesel generator was returned to service at 7:33 p.m. that evening,
      the B pressurizer heaters were restored to operable status at 6: 46 a.m. on
      September 12.
      The net effect was that from 9:50 a.m.         until 7:33  p.m., for a total of 9
      hours and 43 minutes, two trains of pressurizer heaters with back up
      emergency power were not available, in violation of Technical Specification
      3.8.1.1 and Technical Specification 3.4.3.          This is a Violation (50-369/
      85-30-01).
   8. Filter Testing
      During a review of the regulatory requirements associated with the
      preoperational ano surveillance testing of the McGuire Auxiliary Building
      Filtered Exhaust System (VA), it was determined that the preoperational
      testing performed on both units VA systems was apparently nct performed in
      accordance with documented commitments as detailed below.
      McGuire FSAR Section 9.4.2.3 and Table 9.4.2-3 states that the in place                       ,
      testing of the VA systems, specifically the HEPA and charcoal filters, was
      conducted in accordance with Regulatory Guide 1.52 (Revision 2, March 1978).
      Regulatory Guide 1.52 in turn obligates the licensee to ANSI N510-1975.
      These requirements stipulate that the airflow distribution to the HEPA

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      filters and iodine a~osorbers should be tested in place for uniformity
      initially and after maintenance affecting the ' low distribution.               The
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                     testing was to have been conducted in accordance with the provisions of
                     Section 8 of ANSI N510-1975.
                      In reviewing completed pre-operational test TP-0-A-1450-02, the preoperation
                     filter test for auxiliary building, filtered exhaust trains 1 and 2, it
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                     appears that the sections of the procedure associated with the airflow
                     distribution test on both units were deleted prior to performance based on a
                      letter of operability from a vendor.                    The tests were never successfully
                     comoleted. Furthermore, ANSI N510-1975, Section 12.5 In place Leak Test,
                     Absorber, Absorber Stace, Procedure, requires that during the actual perfor-
                     mance of the absorber test, at least four upstream samples and five downstream
                     samples be taken to determine filter penetration. Tne completed preoperational
                     tests for both units i ndicate that only three samples were taken.                              This
                     challenges the viability of the tests.
                      In view of the above findings, it is concluded that the preoperational tests
                     performed on both units VA systems were not performed in accordance with
                     documented commitments.                This is a (Deviation 50-369/85-30-02, 50-370/
                     85-32-01).
                     Ghen the fact that the airflow distribution tests were not performed, and
                     given that the results of these tests could affect the results of other
                      surveillance tests, i.e., the representativeness of the charcoal samples
                     sent in for laboratory analysis, an Unresolved Item (50-369/85-30-03,
                     50-370/85-32-02) will be carried forward pending the resolution of the
                     apparent deviation and the completion of a detailed review of filter testing
                     at McGuire.
         9.          Shift Staffing
                     On Friday, September 6, 1985 at approximately 3:00 p.m. while conducting a
                     control room tour, the Inspector noted that none of the Senior Reactor
                     Operators (SRO) were present who were identified on the shift turnover
                     checklist as being required to be in the control room at the time.                              Upon
;                    questioning the personnel who were there, it was determined that there was
                     an SRO present, fulfilling the requirement of Technical Specification 6.2.
                     Technical Specification 6.2.2 (b) requires that while either unit is in

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i                    moces 1, 2, 3, or 4 at least one licensed SRO snall be in the control room.
                     Station Directive 3.1.9, Relief at Duties of Plant Operation, a procedure
                     which implements the requirements Technical Specification 6.2.2 specifies
                     that in Modes 1-4, one of the individuals designated therein with a double
                     asterisk, shall be designated Control Room Senior Reactor Operator and shall
                     be located within the Control Room. Contrary to those requirements, none of
                     the individuals so designated were present. This constitutes a violation
                     for failure to follow procedure (369/85-30-04, 370/85-32-03).

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    10.   Surveillance Testing
          The surveillance tests below were analyzed and/or witnessed by the inspector
          to ascertain procedural and performance adequacy and conformance with
          acclicable Technical Specifications.          The selected tests witnessed were
          examined to ascertain that current written approved procedures were
          available and in use, that test equipment in use was calibrated, that test
          prerequisites were met, system restoration completed and test results were

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          adequate.
          PT/0/A/4350/08E            EVCC Charger Service Test
          PT/2/A/4403/01B            RN 2B Performance Test
PT/2/A/4252/01 CA Pump #2 Performance Test

j pT/1/A/4350/15A 1A D/G Periodic Test 

    11. Maintenance Observations

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          The maintenance activities below were analyzed and/or witnessed by the
          resident inspection staff to ascertain procedural and performance adequacy
          and conformance with applicable Technical Specifications. The selected
          activities witnessed were examined to ascertain that where applicable,
          current written approved procedures were available and in use, that
          prerequisites were met. equipment restoration completed and maintenance
          results were adequate.
                Work Request                        Title
                86234                SA-48 Turbine Driven CA Pump Steam Supply
                86262                VA Filter Exhaust System                                   j
    12. Open Items Review
The following items were reviewed in order to determine the adequacy of

i corrective actions, the implications as they pertain to safety of i 

          operations, the applicable reporting requirements, and licensee review of
          the event. Based upon the results of this review, the items are herewith
          closed.

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                                                Unit 1                                       Unit 2 (cont'd)                                                    i
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                                              ITEM NUMBER                                    ITEM NUMBER
                                              LER 84-09                                      LER 83-68
                                                                                             LER 83-69
                                                Unit 2                                       LER 83-71
                                              ITEM NUMBER                                    LER 83-72
                                                                                             LER 83-73
                                              LER 83-06                                      LER 83-74
                                              LER S3-19                                      LER 83-75
                                              LER 83-19                                      LER 83-77
                                              LER 83-25                                      LER 83-78
                                              LER 83-26                                      LER 83-79
                                              LER 83-27                                      LER 83-80
                                              LER 83-28                                      LER 83-81
                                              LER S3-30                                      LER 83-82
                                              LER 83-31                                      LER 83-83
                                              LER 83-32                                      LER 83-84
                                              LER 83-33                                      LER 83-85
                                              LER 83-34                                      LER 83-86
                                              LER 83-36                                      LER 83-87
                                              LER 83-37                                      LER 83-88
                                              LER 83-38                                      LER 83-89
                                              LER 83-39                                      LER 83-90
                                              LER 83-40                                      LER 83-91
                                              LER 83-41                                      LER 83-92
                                              LER 83-42                                      LER 84-01
                                              LER 83-43                                      LER 84-02
                                              LER 83-45                                      LER 84-03
                                              LER S3-47                                      LER 84-04
                                              LER 83-48                                      LER 84-05
                                              LER 83-49                                      LER 84-06
                                              LER 83-51                                      LER 84-08
                                              LER 83-52                                      LER 84-09
                                              LER 83-55                                      LER 84-11
                                              LER 83-56                                      LER 84-13
                                              LER 83-58                                      LER 84-14
                                              LER 83-60                                      LER 84-15
                                              LER 83-61                                      LER 84-18
                                              LER 83-62                                      LER 84-20
                                              LER 83-63                                      LER 84-21
                                              LER 83-65                                      LER 84-26
                                              LER 83-66                                      LER 84-29
                                              LER 83-67                                      LER 84-33
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