ML20154P897: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot change)
(StriderTol Bot change)
Line 1: Line 1:
{{Adams
#REDIRECT [[IR 05000341/1988024]]
| number = ML20154P897
| issue date = 09/27/1988
| title = Insp Rept 50-341/88-24 on 880815-0909.Violation Noted.Major Areas Inspected:Implementation of Generic Ltr 83-28 in Areas of Equipment Classification,Vendor interface,post-maint Testing & Reactor Protection Sys Reliability
| author name = Gardner R, Neisler J
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
| addressee name =
| addressee affiliation =
| docket = 05000341
| license number =
| contact person =
| document report number = 50-341-88-24, GL-83-28, GL-85-14, GL-85-22, IEB-81-03, NUDOCS 8810030218
| package number = ML20154P871
| document type = INSPECTION REPORT, NRC-GENERATED, TEXT-INSPECTION & AUDIT & I&E CIRCULARS
| page count = 7
}}
See also: [[see also::IR 05000341/1988024]]
 
=Text=
{{#Wiki_filter:_ ,_ - - _ - - - - . - - - - - - _ - - _ _
                    .
                              ,
                                                                                                                    ,
                                            -
        ..              ,
1
                                                            U. S. NUCLEAR REGULATORY C069tISSION
                                                                                                                    '
,
.                                                                        REGION III
                                                                                                                    L
                                  Report No. 50-341/88024(DRS)
                                                                                                                    '
                                                                                                                    ,
!
                                  Docket No. 50-341                                            License No. NPF-43 :
                                                                                                                    i
                                  Licensee: The Detroit Edison Company                                            .
4
                                                2000 Second Avenue
i                                              Detroit, MI 48224                                                  ,
                                  Facility Name:    Fenni 2
9                                                                                                                  ,
                                  Inspection At:    Fer:ni Site Monroe, Michigan
                                                                                                                    c
;
                                    Inspection Conducted: August 15 through September 9, 1988                      j
l                                                  k.h hM< p                                              9!27 I8
                                                                                                                    ;
i
                                  Inspector:      J. H. Neisler                                                    1
                                                                                                                    t
i                                                                                                    Date
                                                          %W
                                                  Ronald N. Gardner, Chief                              9[27fff
j                                Approved By:
-
                                                  Plant Systems Section                              Date
I                                                                                                                  ;
                                  Inspection Suninary
)
                                  Inspection on August 15 through September 9, 1988 (Report No. 50-341/88024(DRS)) f
3
                                  Areas Inspected: Routine announced inspection of licensee's implementation of    !
j                                  Generic Letter 83-28 in the areas of ecuipment classification, vendor            i
                                                                                                                    "
t                                  interface, post maintenance testing anc reactor protection system reliability.
                                    IE Bulletins and open item followup. (25564)(25595)(92700)
                                                                                                                    '
l                                  SIMS 75 (B-77, B-78 B-79. B-80, R-86, B-87, B-88, B-92, B-93) MPA-C-02,          ;
;
j                                  Rssults: Of the four areas inspected, no violations or deviations were          !
i                                  identTTied in three areas. One violation was identified in the remaining area  l
1                                  (inadequate procedures to control vendor technical information). Within the    i
j                                  scope of this report a weakness was observed regarding the inadequate control    i
;                                  of vendor equipment technical information. No significant strengths were        i
j
                                  observed,                                                                        j
l
:
i                                                                                                                  i
i                                                                                                                  l
i                                                                                                                  i
i                                                                                                                  L
  l                                                                                                                I
i                                                                                                                  ;
.
                                                                                                                    .
  li
                                $BASBE$SSShe
                                  O                                                                                ,
                                                                                                                    '
  )
  t
                                                                                                                    k
 
                                    .              .                  -.          .  . . _ .
      .
          .
;  -
        .
"
                                                DETAILS                                          -
                                                                                                ,
                                                                                                '
'
            1. Persons Contacted
-j
              Principle Licensee Employees                                                      [
,              *S. G. Catola, Vice President, Naclear Engineering                                ,
i              *W.  S. Orser, Vice President, Nuclear Operations                                i
;              *D. R. Gipson, Plant Manager                                                      ;
              *P. Anthony, Compliance Engineer
              *T. Riley, Supervisor, Compliance                                                ,
              *R. Nathews, General Supervisor, Instrument and Controls                          ,
              *C.  Gelletly, Director, Nuclear Engineering
              *R.  Stafford, Director, Nuclear Quality Assurance
'
              *L. Goodman, Director, Nuclear Licensing
i              *T. Musseman, Supervisor, Nuclear Training
,
                G. Shukla, Licensing                                                            :
,
                J. Pendergast, Licensing                                                        j
j              A. Elibe, NPRDS                                                                  ,
'
                G. Booker, Production Information Center
;              D. Delk, Supervision, QA Programs                                                [
;              R. Bailey, Supervisor, Production QA                                            1
i              J. Kepus, Environmental Programs Coordinator
,              B. Wickham, Supervisor, Maintenance Programs                                    .
!              B. Catanese, Maintenance Support Supervisor                                      i
1              R. Ballis, Engineering Supervisor !&C
                R. O'Sullivan, Surveillance Coordinator
l
!              * Denotes those persons attending the exit interview.                            l
t
l          2. TI 2515/64RI (SIMS 75) (Closed)                                                  :
;
l
'
              a.    Equipment Classification                                                    !
                                                                                                i
f                    The inspector selected four components in the reactor protection            l
l                    system and nine components in the core spray system for                    i
!                    examination. The components selectt.d were:                                ;
                                                                                                ,
i
                    Reactor Protection System                Core Spray System (E2Q            !
!                    Mode Switch                              Core Spray Pump C001A              ,
!                    Scram Auxiliary Contactor                Core Spray Pump Motor              ,
;                    Pilot Valve Solenoid                    Core Sara / Pump Circuit          !
l                    Manual Scram Switch                        Breater
!                                                            Flow Transmitter N006A
!
                                                              Pressure Transnitter N007A
                                                              Notor Operated Valve F036A
l>
                                                              Motor Operated Valve F005A
                                                              Check Valve F003A
                                                              Ficw Element FE-N001A
:
!
i
                                                  2
 
  - - - - - - - - - - .    -
                                                                                                    ,
                        .
                          .
            .
                              For the selected components, the inspector performed the following
                              reviews:
                              (1) The inspector reviewed the licensee's safety-related component
                                  list. At Fermi, the Q-List was replaced by the Fermi Central
                                  Component Data Base (CECO), a computerized listing that is used
                                  to identify safety-related components. The inspector selected
                                  several components from system drawings and verified that these
                                  components were properly identified in the data and that they
                                  were correctly classified as safety-related or non-safety-related
                                  components.
                              (2) Todeterminethelevelofplantmanarjementoversight,the
                                  inspector reviewed procedures contro ling the classification of
                                  structures, systems and components; preventive and corrective
                                  maintenance; modifications; procurement, storage and issue;
                                  inspection and testing of safety-related items; quality
                                  assurance procedures, audits and surveillances; and corporate
                                  level procedures and d:rectives for activities impacting
                                  safety-related structures, systems and components.
                              (3) The inspector reviewed surveillance procedures, calibration
                                  procedures, maintenance procedures and instructions functional
                                  test procedures and storage procedures to verify that the
                                  licensee has issued adequate procedures and instructions for
                                  the perfomance of safety-related activities.
                              (4) The inspector reviewed the licensee's program and implementing
                                  procedures for the training and indoctrination of technicians,
                                  craft workers, staff engineers, planners and supervisors whose
                                  duties include safety-related activities. Training records
                                  indicated that the above personnel were being trained according
                                  to applicable procedures.
                              (5)  The inspector reviewed 12 audit reports and 19 surveillance
                                  reports dccumenting Quality Assurance audits and surveillances
-
                                  involving safety-related activities. The quality assurance
                                  organization maintains a schedule of planned audits and
                                  surveillances of safety-related activities at the plant and at
                                  offsite vendor and supplier organizations.
;
l
                              (6)  The corrective action program for safety-related activities is
                                  described in the licensee's Quality Assurance Manual and
                                  implementing procedures. The inspector's review of corrective
                                  action for audit and surveillance findings listed in the audits
                                  and surveillances in (5) above revealed that corrective action
                                  for those findings was timely and adequate.
                              (7) Review and evaluation of infonnation concerning malfunctioning
                                  equipment is controlled by the licensee's procedure
i                                  P0M 12.000.059, "Operating Experience Assessment," by Deviation
i                                  Events Reports and Nonconfonnance and Corrective action
:
I
                                                            3
I
 
                                                              _
                                                                                            _
                        .
                                                                                                    l
          .
                                                                                                    l
                                  procedures.  Included in the reviews and evaluation is the
                                  detemination of the suitability of the equipment to perform      j
                                  its design function.                                              ;
                            (8) The inspector reviewed modification packages involving the
                                  reactor 3rotection system and the core spray system. The
                                  design c1anges, work requests, drawings, inspection documents
                                  and procurement packages were correctly identified as to their
                                  safety classification.
                          b. Vendor Interface
                            The inspector reviewed procadures controlling the licensee's vendor
                            equipment technical information program. The procedures reviewed were
                            FMD 2.5.10. Revision 0, "Document Control," and NE 2.5.10, Revision 3
                            "Vendor Manuals". These procedures have no requirement to collect,
                            review, and control existing vendor technical infomation pertaining
                            to plant safety-related structures, systems, and cuoponents that are
                            in possession of individuals, shops, or departments onsite. The
                            inspector observed vendor information in each building visited
                            but there was no indication that the infortnation had been reviewed
                            to determine its applicability to plant components. During
                            discussions with licensee personnel, the inspector was infomed that
                            individuals and shops were in possession of uncontrolled and
                            unreviewed vendor manuals.
                            One of the manuals the inspector selected for review was the vendor
                            manual for the core spray pump discharge check valve, a safety-related
                            code valve that was included in the licensee's inservice inspection
                            program. The inspector was informed by personnel in the plant
                            Information Center (PIC) that the manual was in use and had not been
                            reviewed and approved. The licensee issued DER 88-1532 after the
                            inspector had identified the unreviewed and unapproved vendor manual.
                            Based on the above examples, the inspector determined that Fermi 2
                            procedures controlling the vendor equipment technical infomation
                            program are not adequate to assure that current, approved
                            technical information is used in the performance of safety-related
                            activities.  This is a violation of 10 CFR 50, Appendix B,
                            Criterion VI (50-341/88024-01).
                          c. Post Maintenance Testing
                            The inspector selected components from the reactor ]rotection system
                            dnd the core spray system for review to ascertain w1 ether the licensee
                            was implementing i post maintenance test program.
                            For the selected corrponents, the inspector determined that:
                            (1) Written post maintenance test proceduros and checklists have
                                  been developed by the plant staff. The inspector reviewed
                                  procedures, tests, and conpleted work requests to verify that
                                  post maintenance testing was being accomplished on the selected
                                  components in accordance with the licensee's cennitments.
                                                            4
- _ ________________ ___
 
                  _ - - - - - - - _ - - - - -
                                                                                                          ,
                                                      - - -
      .
        .
    .
                  (2) Criteria and responsibilities for maintenance approvals and for
                                        designating activities as safety-related or non-safety-related
                                        have been established in work request and modification
                                        procedures. Criteria for post maintenance testing and
                                        inspections are delineated in work request procedures, quality
                                        inspection procedures and maintenance support planning
                                        procedures.
                  (3) Methods for performing functional testing following maintenance
                                        activities have been developed and are delineated in published
                                        plant operations and maintenance surveillance procedures.
                  (4) The inspector reviewed 26 compiled maintenance work requests
                                        and their supporting documentation. The work requests were
                                        appropriately classified, properly approved, and the persons who
                                        perfonned the activity and inspections or verifications were
I                                        identified on the work requests and supporting documentation,
i
l                No violations or deviations were identified.
l
            d.  Reactor Trip Systems Reliability
                  At Fermi II, on-line functional testing of the scram pilot
!                solenoid valves is performed with the prottetion rystem instrument
j                channel functional tests at the frequency required by the plant
l                Technical Specifications. The inspector reviewed test procedures
                  and test results for the following functional tests:
                  Reactor Vessel Dome Pressure - High
                  Reactor Vessel Water Level - Low
                  Reactor Vessel High Steam Line Pressure - High
                  Average Power Range Monitor High Flux Trip
                  Backup Manual Scram Functional Test
                  Intermediate Range Monitor Trip
                  Manual Scram
                  MSIV Closure Functional Test
                  Main Steam Line High Radiation
                  Drywell Pressure - High
                  Scram Discharge Volume High Level
                  Turbine Control Valve /Turbinc Stop Valve
                  The procedures appeared to be adequate and the test data dates
                  indicated that the testing was being accomplished as required by
                  Technical Specifications.
                                                                                                            1
          3. Tl 2515/95 (MPA-C-02) (Closed)                                                                )
                                                                                                            i
            The inspector verified by review of as-built drawings 61721-2095-30,                          l
            Revision X, 61721-2101-02, Revision n. 61721-2101-01, Revision L and                          i
            0!?21-2095-37, Revision G that the licensee has installed reactor                              l
            recirculation puup trips that are actuated by either low reactor water
            level or high reactor vessel pressure.
                                                                                  5
  .
                                                              _ _ _ _ - _ _ _ _ _
 
                                                                                      ,
  .
    .
..
      4. Genericletter85-22(Closed)
          Potential for loss of post-loca recirculation capability due to
          insulation debris blockage. The inspector reviewed the licensee's
          evaluation of potential blockage of suction strainers in the drywell and
          torus. The bulk of the insulation is metallic reflective insulation and
          the remainder is totally stainless steel encapsulated fibrous material.
          Suction strainers are installed at a 45-degree angle in the torus above
          the bottom of the pool or halfway between the minimum water level and the
          pool bottom. The licensee concluded that the material used and the location
          of the strainers at Fennt would not result in significant blockage. This
          item is closed.
      5. Generic Letter 85-14 (Closed)
          Connercial storage at power reactor sites of low level radioactive waste
          not generated by the utility. Fermi does not store low level waste not
          generated by the utility onsite. Discussions with l'censee personnel
          revealed that the site does not plan to store waste generated by others
          at the Fermi site. This item is closed.
      6. Licensee Event Report 86-044-01 (Closed)
          potentially degraded torus relief line isolation capability during
          postulated accident event. An environmentally induced failure of a limit
          switch for a drywell vacuum breaker valve can be postulated to occur
          under harsh environtrental conditions. This can result in degradation of
          the division 11 power supply circuit and cause the torus vacuum breaker
          isolation valve to fail open. The licensee has modified the drywell
          vacuum breaker valve limit switch circuit on the "close" side to
          limit the maximum current to ground. This change will prevent shorts to
          ground from being cleared by the pcwer supply fuse and removing power
          frcm position indication for the vacuum breaker valves or the pilot vulve
          solenoid on the air operated torus vacuum breaker valve. This item is
          closed.
      7. Inspection and Enforcenwnt Bulletin 81-03 (Closed)
          Flow Blockage of Cooling Water to Safety System Components by
          Corbicula sp. (Asistic Clans) and Mytilus sp. (Mussels). The
          inspector reviewed the licensee's program for detecting the presence
          of corbicula and sampling results for the years 1987, 1906 and 1985.
          The presence of corbicula was not detected in any of the sarrples during
          the three sarnple years reviewed. This item is closed.
      8. Open Its 85003-01 (Closed)
          Clarification of differences between Technical Specificatior and ASME
          Section XI requirements for declaring valves inoperable. The licensee
          has revised applicable procedures to remove the ASME requirerrent frorn the
          surveillance procedures. Surveillance Procedure 24.207.10 was repeated
          using the proper checklists and indepetident position verification
          performed >y a person other than the person perfonning the surveillance.
          This item is closed.
                                              6
 
_ _ _ _ _ - _ _ _ _ _ _ _ _ _ _                    ____          _      __              _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
                                  .
                                      .
                              ..  .
                                        9. Exit Interview
                                          The inspector met with licensee representatives listed in Paragraph 1 and
                                          sumarized the scope and findings of the insprtion. The inspector also
                                          discussed the likely informational content of che inspection report with
                                          regard to documents or processes reviewed by the inspector during the
                                          inspection. The licensee did not identify any such documents or
                                          processes as proprietary.
                                                                                                                                                ,
                                                                                                                                                4
                                                                                                                                                l
                                                                                                                                                !
                                                                                                                                                (
                                                                                                                                                P
                                                                                                                                                l
                                                                                                                                                l
                                                                                                                                                f
                                                                                                                                                f
                                                                              7
                                                                                                                                          _ ____
}}

Revision as of 23:31, 10 December 2024

Redirect to:

Retrieved from "https://kanterella.com/w/index.php?title=ML20154P897&oldid=4134723"