IR 05000413/1987033
| ML20236M332 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 11/04/1987 |
| From: | Lesser M, Peebles T, Van Doorn P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20236M319 | List: |
| References | |
| 50-413-87-33, 50-414-87-33, NUDOCS 8711130096 | |
| Download: ML20236M332 (9) | |
Text
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ATLANTA. GEORGI A 30323
\\...../ Report Nos.: 50-413/87-33 and 50-414/87-33 Licensee: Duke Power Company 422 South Church Street j Charlotte, NC 28242 Docket Nos.: 50-413 and 50-414 License Nos.: NPF-35 and NPF-52 l Facility Name: Catawba 1 and 2 Inspection Conducted: September 26 - October 25, 1987 /f/8/ / //W77 Inspectors: 'Tr.
K'. Va n" D~o o rn /~ Haf,4 Signed /"S ' Le's se rAi6 b /L w Wr7 [ Oat / Signed M.
. Approved by: A // V
T., A. Peebies,' Section Chief Ddte / Signed Projects Branch 2
' Division of Reactor Projects SUMMARY l ' l Scope: This routine, unannounced inspection was conducted on site inspecting i in the areas cf review of plant operations; surveillance observation; i maintenance observation; review of licensee nonroutine event reports; Part 21 reports; refuelirg activities; and followup of previously identified items.
Results: Of the seven (7) areas inspected, no apparent violations or , l deviations were identified.
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' . . l REPORT. DETAILS 1.
Persons Contacted Licensee Employees "J. W. Hampton, Station Manager i ,
- H. B. Barron, Operations Superintendent W. F. Beaver, Performance Engineer W. H. Bradley, QA~ Surveillance S. Brown, Reactor Engineer B. F. Caldwell, Station Services Superintendent R. N. Casler, Operat'ng Engineer i
R. H. Charest, Station Chemistry Supervisor
- M. A. Cote, Licensing Specialist T. E. Crawford, Integrated Scheduling Superintendent
) W. P. Deal, Health Physics Supervisor j C. S. Gregory, I. & E. Support Engineer j
- C. L. Hartzell, Compliance Engineer i
J. Knuti, Operating Engineer -{ " F. N. Mack, Project Services Engineer W. W. McCollough, Mechanical Maintenance Supervisor C. E. Muse, Operating Engineer.
F. P. Schiffley, II, Licensing Engineer )
- G. T. Smith, Maintenance Superintendent J. Stackley, I. & E. Engineer q
- D. Tower, Shift Operating Engineer j
- R. F. Wardell, Technical Services Superintendent J. W. Willis, Senior QA Engineer, Operations j
l Other licensee employees contacted included technicians, operators,- ' mechanics, security force members, and office personnel.
- Attended exit interview.
2.
Exit Interview The inspection scope and findings were summarized on October 23, 1987, with those persons indicated in paragraph 1 above.
The inspector described the areas inspected and discussed in detail the inspection findings.
No dissenting comments' were received from the licensee.
The licensee did not identify as proprietary any of the materials provided to .j or reviewed by the inspectors during this inspection.
The following new items were identified: Unresolved Item 413, 414/87-33-01: Two l Channels of Valve Position Indication For PZR PORV's and PORV Block Valves Not Installed As Required By T.S. 3.3.3.6.
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Licensee Action-on-Previous Enforcement Matters,(92702) ' 'l i .'a. (CLOSED) Unresolved Item 413/86-15-04: ; Review > ofC Training andL l Guidance for Performing Reactor Trip Reviews. Followup ofethis item was performed and documented.in. NRC Report No. 413,414/87-25.
However, the item was mittakenly listed as 414/86-15-04. and, ' therefore, is being re-closed in_this' report.
b.
(OPEN) Unresolved. Item 413,414/87-10-01: Si.'nhle- ' Failure ! Vulnerability of the Nuclear. Service, Water. System..The inspectdr j conducted a detailed Nuclear Service Water (RN). System Procedure,. j (OP/0/A/6400/06C) history review. Appropriate procedure changes were l which have been previously discussed between: NRC and a the' licensee.. ' d apparently: implemented : addressing the vari ~ous. specia11RN alignments? J Shared Unit alignments were first ' addressed 'in Technical. Memorandums d 16-02. an.d 16-03, issued on February 26, 1986. and. March.4, : 1986', , respectively.
A. procedure change incorporating _ these. 'special _ > l alignments was issued on May 15, 1986.
A change to _ implement . realignment of an unaf fected RN pit to the Standby Nuclear Service Water Pond (SNSWP) when a Diesel Generator 'is' out_ of servii:e greater-than 72 hours was issued on March 5,1987. The procedure ' change
which removed power from the SNSWP valve was not issued-until April 3, 1987.
Further review is necessary to determine 11f power - -I should have been removed during the March time frame since the' normal accepted practice to place a valve in < a passive failure mode is' to j remove power.
The licensee will be submitting :a_ Licensee Event .[ ~ Report (LER) on this issue.. This item remains open pending the.LER ' and further NRC review.
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(OPEN) Violation 413/87-20-03: Inadequate Investigation of Isolated
Containment Pressure Channel. The. licensee responded ~to this' item on ~ August 28,1987 -denying the violation.. The !NRC rejected :the denial d in a letter dated September 30, 1987. The in'spector discussed the _ NRC concerns with licensee personnel.
The licensee indicated that-another response would be submitted admitting ~ the violationmand' documenting appropriate corrective action to be. implemented. ' This item remains open pending the additional response, d.
(CLOSED) Violation 414/87-15-01: Channel Check on ' Auxiliary Feed Flow Instrumentation Inadequate to Meet Specified Acceptance Criteria Required by Procedure.
The licensee responded ~ to this item -in correspondence dated October 14,.1987.
The inspector reviewed the corrective action taken and observed the performance of the~ channel , check on one channel of Auxiliary Feed Flow ' which partially ~ l i calibrates the input transmitter.
Based on this the item is closed.' e.
(CLOSED) Violation 413,414/87-25-02: Failure to-Demonstrate Operability of Offsite Power Sources Within Required-Time Frames.
The licensee responded to this item in correspondence dated
October 14, 1987..The inspector : reviewed the corrective '. actions"
- i taken and considers this item closed.
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(CLOSED) Unresolved Item 414/87-25-04i-Deletion ~ of Incident Investigation Report Conclusions From LERJ Without Station - Manager q Approval.
Revision 2-to LER A14/87-15 was issued by the. licensee ll > which added ' a' previously deleted conclusion' from Lthe Incident: ' , ... Investigation Report- (IJR), ' Typically. - the. station subinits the- ' ' completed IIR to. Corporate Licensing which is ther, used. to gewrate ' -4 R' the LER.
Since ' Corporate Licensing Personnel do not per' form the ' f actual investigation, Lany ; changes they'.wish. to: make to the Vreport) [ must be discussed with Catawba. Safety" Review? Group.(CSRG) tand. at t . approved by the Station. Manager-(possibly in the fform of a' revised /9- ' .IIR).
This relationship.betweer, CSRG ' and, Corporate: Licensing must- -exist and was discussed with applicable personnelfwho?egreed('; Based upon the revised LER, this Litem 1.s closeri.
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, . No violations or deviations were identified.
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Unresolved Items * ' ,
A new unresolved item is identified in paragraph 5.
5.
Plant Operations Review (Units 1 & 2) (71707 and 71710)- a.
The inspectors reviewed ' plant operations. througho t - the: reporting ~ period to. verify conformance withL regulatory requirements,. Technical-i Specifications (TG), and administrative co'ntrols. Control room logs,
' danger ' tag logs; Technical Specification Action? Item Log; andithe removal and restoration log were routinely. reviewed. Shif,t turnovers , were observed to verify that they were; conducts.d in accordance with
' approved procedures.
' The inspectors verified by observation and interviews,-the measures.
' , taken to assure physicali protection of; the' facility met current-
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,1 ' requirements.
Areas 'itispected included. the security' orgafihati.on,; ' , the establishment and maintenance of gates, - doors,1 =and ' isolation a
zones ' in - the proper condition,= that access control and badging were '
1 proper and procedures followed, ' ' _ q In addition-to the areas discussed. above, thi areas toured were - ..' observed for fire prevention and protection activities, These included such things,as combustible. material' control, fire' protection systems and materials,- and fire protection associatedE with maintenance 1 -activities.
The inspectors reviewed Problem. ' Investigation Reports to determine if-the licensee was appropriately-- !yT , . documenting ~ problems and implementing app'ropriate. corrective actions.
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- An Unresolved Item is a matter about which more information is required l to
! determine whether it is acceptable.or may involve'a' violation.
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. b Unit 2 Summary ' The unit started the period at 10C% power. Power was reduced to 95% on or about October 13 due to problems with the C Steam Generator Feed Regulation Valve not passing enough flow. The Unit operated for i the remainder of the period at or about 95% power. Flow through the' Feed Regulation Velve is stable and efforts to identify in electrical problem have been unsuccessful. Plans to inspect for flow blockage are scheduled and will be done when the unit is shut down.. t c.
Problem Investigation Report (PIR) 0-C87-0275 identified that only j one channel of valve position indication exists on each pressurizer Power Operated Relief Valve (PORV) and PORV Block Valve, although TS 3.3.3.6 specifies that 2 channels per valve be operable.
Design i engineering concluded that because two' indications of valve position exist, (control board indicatw light and aLcomputer point) that the TS is being compliv.d with.
However, both of these indications come ! off the same limit switch therefore they are not independent channels as defined by Section 7.5.3.2 of the Catawba FSAR, which states that a channel is a group ofe components' required to generate a single j information signal.
Although this was recognized in the PIR, the conclusion' reached is incorrect if a 'strt:t definition of a channel n used. Related to this issue is the method the~ license'e employs to perform the monthly channel check required by TS 4.3.3M on thess. )' valves. To channel check PORV Block valve position, PT/2/A/4600/03A requires the operator to compare tiie valve position indicating light with the valve position select switch.
The PORV',s are checked by
comparing the valve position indicating light with a downstream, high j temperature alarm.
These methods do not constitute acceptacly channel checks.
Apparently adequate channel ' checks cannot be ) performed on these valves since only one channel of' valve. position ' exists on each valve.
Therefore the licensee may not be in compliance with the TS.
The requirements for the valve position 'j indication are a result of TMI-2 Action Plan Item II.D.3 and it - ; appears from section 7.5.2.2 of the Catawba SER that the licensee's j response to this item was approved. The' licensee stated that Nf: was aware of the specific design and a standard TS was 'being applied which doesn't accurately apply to the specific design.
However, it
may not have been clearly understood by NRC that the two indications of valve position were from the same limit switch, The licensee must resolve this issue by providing two channels of valve position indication or by amending the TSs whichever is more appropriate.
This i s Unresolved Item 413, 414/87-33-01: Two Channels of Valve Position Indication for PORV's and PORV Block Valves Not Installed As Required by TS 3.3.3.6 pending resolution by the licensee, d.
The inspectors performed a detailed walkdown of the Nuclear Service Water System on both Units.
No violations or deviations were identified.
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Surveillance Observation (Units 1 & 2) (61726) a.
During the inspection period, _ the inspecter verified plant operations j were in compliance with various TS-requirements.
lypical of these j requirements were confirmation of compliance with the TS _ for reacter q coolant chemistry, refueling water tank, ' emergency power systems, y safety injection, emergency safeguards systems, control room l ventilation, and direct current electrical power sources.
The i inspector verified that surveillance testing was performed' in d accordance with the approved written procedures, test instrumentation was calibrated, limiting conditions for operation were met, appropriate removal and restoration of-the affected equipment was accomplished, test results met requirements and were reviewed by personnel cther than the individual directing the test, and that any i deficiencies identified during the testing were properly reviewed and ! resobed by appropriate management personnel.
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The.following surveillance activities were either reviewed or observed wholly or in part: l l PT/2/A/4600/02A Mode 1 Periodic Surveillance Items PT/1/A/4200/09 Train B ESF, LOCA with Blackout Test j IP/1/A/3122/02 ICCM System Calibration ) PT/1/A/4200/02D Refueling Containment Integrity Verification j ! No violations or deviations were identified.
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Maintenance 0 observations (Units 1& 2) (62703) a.
Station maintenance activities of selected systems and components ] l were observed / reviewed to ascertain that they were conducted in ) l accordance with requi rement s'. The inspector verified licensee I conformance to the requirements in the following areas of inspection: !
l the activities were accomplished using approved procedures, and functional testing and/or calibrations were performed prior to j , ' returning components or systems to service; quality control records i were maintained; activities performed were accomplished by qualified personnel; and materials used were properly certified. Work requests were reviewed to determine status of outstanding jobs and to assure that priority i s ast '., ned to safety-related equipment maintenance ' which may effect system performance.
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The following maintenance activities were either reviewed or observed l wholly or in part.
OP/0/A/6200/22 IB NS Heat Exchanger Cleaning ,
PT/0/A/4400/08 A and B Train RN Flow Balance 004434 SWR Preventive Maintenance on 1KD-21 37524 OPS Inspect and Repair 2CA-149 Not Opening 3504MNT-3511MNT Replace External Closing Assist Springs on ISM-001, 1SM-003, ISM-005, 1SM-007, 2SM-001, , 2SM-003, 2SM-005, 2SM-007 l l .1 I I o______---------------- - - - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _. - _U
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, " l-l I No violations or 'dev'iatio'ns were identified.- 8.
Reviow of Licensee Nonroutine, Event Reports'and Part 21' Reports
,. (Units 1 & 2) (92700) " a.
The below listed Licensee Event Reports, (LER)1were. reviewed to-determine if the information provided met NRC. requirements...The determination included: adequacy of-description, verification of . compliance with Technical Specificat. ions and regulatory require'ments, corrective action taken, existence of potential! generic problems, reporting requirements satisfied, and, tho. relative safety.
significance of each event.
Additional inplant l reviews.and I discussion with plant personnel, as appropriate, were' conducted 'for I those reports' indicated by an (*). The following LERs are closed:
- LER 413/87-34 Reactor Trip Breaker Open-with Unit:1 in Hot:
Standby due to Failure of Source Range Neutron.
Detector during a Unit' Shutdown.
I J LER 413/87-35 Potential Control Room Area Ventil'ation and Chilled Water System Inoperability due'to.a Procedural Deficiency.
- LER 414/87-09 Rv.2 Containment Air Return Isolatio.n Dampers
.I Actuated due'to Defective Procedure.
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- LER 414/87-15 Rv.2 Containment Air Return Isolation. Dampers
' j Actuated due to Defective Procedure.
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- LER 414/87-21 Reactor Trip Resulting from Condensate-Transient due to Unknown Cause.
- LER 414/87-25 Reactor Trip due to~a Steam Generator Overfill because of Personnel ErrorsLand a Management Deficiency, b.
LER 413/87-32 reported an event where missed retests were discovered .) on two 125 VDC batteries EBC and' EBD.
The licensee declared both-J batteries inoperable and applied TS 3.8.'2.1. Action Statement e.
appeared to apply to the situation, however, confusing. wording in the .j Action Statement caused the licensee to conservatively. enter TS 3.0.3
requiring shutdown within. 6 hours.
One battery was' able~ to L be j properly retested within the time ' limit and ' TS - 3.0.3 was exited, however, Action Statement e, remains inconsistent.. The~ inspector - discussed the intent.of the statement with K. Jabbour and J. Lazevnick of NRC:NRR. In' order for. Action. Statement.e. to' apply and allow-two batteries to. remain inoperable for; 72 hours. and -allow.
the unit to remain in-operation, one of:.the following two_ conditions must be' met: EBA and EBC and. their chargers 'be operable' or -EBB and - EBD and their chargers be operable. The intent is to have one train < f' _ __ _ _. _. _. _ _. _ _ _. _ _. _ _. _ _ _ _ _ _
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i ' . of batteries completely operable. The Action' Statement should not include the "or" statement when referring to the requirement that the ! charger also be operable.
NRC:NRR personnel indicated they would consider whether a change to the TS is necessary. In this particular event the licensee appropriately entered TS 3.0.3 because none of J the Action Statements applied.
The licensee will issue a TS ] interpretation to eliminate confusion on.this TS.
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Part 21 Reports i (CLOSED) P21-86-01 (Units 1 and 2): Atwood and Morrill Main Steam Isolation Valves Spring Failure.
The inspector verified that the licensee replaced the subject springs.
No violations or deviations were identified.
) 9, Refueling Activities (Unit 1) (60710) l Unit 1 started the period operating at 100% power. On October 3, the unit , shutdown in preparation for its second refueling outage scheduled to last
until November 30.
Mode 4 was entered at 1858 on October 3 and Mode 5 entered at 0722 on October 4.
During B train Engineered Safety Features (ESF) Testing, the 18 diesel generator failed to operate successfully when attempting an emergency start. Troubleshooting efforts could not localize the problem and were eventually postponed to commence schedule engine maintenance.
The diesel generator must be demonstrated operable prior to commencing work on the 1A diesel generator.
The inspectors will monitor the licensee's actions. On October 18 Mode 6 was entered at 2300, the ! vessel head was lifted and filling of the refueling cavity was started, ) however excessive leakage through the sandbox covers (vessel nozzle access ports) occurred and the refueling cavity had to be drained again to effect repairs.
The inspectors verified that Technical Specifications applicable to Mode 6 were met, fuel handling equipment testing was performed, proper radiological controls, housekeeping and foreign material exclusion practices were met and water level control practices were followed.
No violations or deviations were identified.
10.
Previous Identified Inspector Findings (92701) a.
(CLOSED) IFI 413/86-17-02, 414/86-18-03: Develop Procedure to Describe the Process of Handling IE Notices and IE Bulletins. The inspector reviewed Nuclear Production Department Directive 4.8.1(s) Operating Experience Program Description.
IE Information Notices are received, screened, and distributed by the Operating Experience Management and Analysis (0EMA) Section. The General Office Licensing Section is responsible for IE Bulletins and Generic Letters.
Based on the program description in this directive, this item is closed.
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(OPEN) IF1 413/86-27-01, 414/86-30-01: Followup' on Analysis of
Bussman Type FNA Fuses for Reliability.
The licensee has continued to perform weekly inspections of safety related FNA fuses ' to justify continued operation and to obtain reliability data.
On August 15, 1987, during ' performance of the . inspection (007866 SWR), fuse 1EATC13/A27 was. discovered to' have j mechanically failed. The licensee was not prompt in identifying the .j potential inoperable equipment' and did not declare applicable .- equipment (one PZR P,0RV) inoperable until. August 17, 1987.
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Fortuitously the blown fuse onlylmade certain. portions of the PORV.
(safety related nitrogen backup) inoperable which were not. required for the valve to perform its safety function in the mode the unit was in. After discussing the incident with IAE personnel, the Standing Work Request was revised to require timely resolution of systems affected by a failed fuse.
The inspector reviewed licensee actions for another failed fuse discovered on October 11, 1987 and concluded they were adequate. This item still remains open pending completion ' of data collection and licensee analysis or completion of fuse replacement with a new design.
j No violations or deviations were identified.
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