IR 05000302/1978010
| ML19317G269 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 05/15/1978 |
| From: | Dance H, Wessman R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19317G257 | List: |
| References | |
| 50-302-78-10, NUDOCS 8002280893 | |
| Download: ML19317G269 (9) | |
Text
UNITED STATES
- ""4g NUCLEAR REGULATORY COMMISSION
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Report No.: 50-302/78-10
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Docket No.:
50-301 License No.: DPR-72 Licensee:
Florida Power Corporation 3201 34th Street South P. O. Box 14042 St. Petersburg, Florida 33733 Facility Name:
Crystal River 3
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Inspection at:
Crystal River site, Crystal River, Florida
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Inspection conducted: April 24-28, 1978 Inspector:
R. H. Wessman Accompanying Personnel:
F. J. Long (April 27, 1978)
H. C. Dance (April 27-28, 1978)
Reviewed by:
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H.'C.
Dance, Chief
'Dats Reactor Projects Section No. 1 Reactor Operations and Nuclear Support Branch Inspection Summary Inspection on April 24-28, 1978: (Report No. 50-302/78-10)
Areas Inspected:
Routine, unannounced inspection of plant operations and outage activities; followup on previous noncompliance items and unresolved items; and facility tours.
Announced management meeting on April 27, 1978, to discuss FPC-licensed activities; review enforcement history; review recent inspection results; and to discuss NRC organizational relationships and communication philosophy. The inspection involved 58 inspector-hours on site by three NRC personnel.
Results:
Of the five areas inspected one item of noncompliance was identified in one area (Deficiency:
Failure to submit Monthly Operation Report as required by Technical Specifications (78-10-01)).
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.RII Rpt. No. 50-302/78-10 I-1
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I DETAILS I Prepared by:2N h_
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R. H. Wessesn, Reactor Inspector Date Reactor Projects Section No. 1
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Reactor Operations and Nuclear Support Branch
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gpril24-28,1978 Dates of Inspect n:
Reviewed by:
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H. C. Dance, Chief
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Reactor Projects Section No. 1 Reactor Operations and Nuclear
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Support Branch
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1.
Persons Contacted I
Florida Power Corporation (FPC)
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- G.
P. Beatty, Jr., Nuclear Plant Manager
- W. R. Nichols, Operations Superintendent
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F. McKee, Technical Services Superintendent
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- J. L. Harrison, Assistant Chemistry / Radiation Protection Enginect
- J. C. Wright, Chemistry / Radiation Protection Engineer
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W. R. Klein, Reactor Engineer J. Cooper, Compliance Engineer
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- G. M. Williams, Compliance Plant Engineer
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R. Westafer, Maintenance Superintendent C. G. Goring, Compliance Auditor P. L. Breaux, Nuclear Shift Supervisor W. M. Marshall, Nuclear Operator
M. P. Holmes, Nuclear Operator K. O. Vogel, Operations Engineer i
- Denotes those persons at Exit Interview.
2.
Management Meeting - April 27, 1978 The NRC met with Florida Power Corporation on April 27, 1978, to discuss FPC-licensed activities.
This meeting was convened at the request of Region II to review Crystal River 3 enforcement history i
and licensee events; review recent inspection results; and to discuss NRC organizational relationships and communication philosophy.
Attendees included:
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F. J. Long, Chief, Reactor Operations and Nuc >sr Support
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Branch, NRC H. C. Dance, Chief, Reactor Projects Section No. 1, NRC R. H. Wessman, Reactor Inspector, NRC
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W. P. Stewart, Director Power Production, FPC G. P. Beatty, Jr., Nuclear Plant Manager, FPC E. C. Simpson, Nuclear Support Specialist, FPC Selected members of the Crystal River 3 Staff 3.
Licensee Action on Previous Inspection Findings The inspector reviewed various open items, unresolved items, and licensee responses to items of noncompliance.
The status on these items is indicated below:
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- a.
(0 pen) Unresolved Item 77-6/2, Loss of Power to ICS.
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item was reviewed in December 1977 (RII Rpt. 77-25). MAR 77-10-09 was initiated in October 1977 to resolve this item but the MAR had not been issued at the time of this inspection.
b.
(Closed) Unresolved Item (RII Rpt. 77-9), Emergency Feedpump Actuation Testing.
This unresolved item is closed by the issue of Technical Specification Amendment No. 11 and the
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incorporation of Technical Specification requirements into
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surveillance procedures.
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c-(Closed) Outstanding Item (Details II, paragraph 6 of RII Rpt. 77-11), Review of Surveillance Program.
The licensee has taken actions relating to surveillance testing control as described in RII Rpt. 77-17.
Additional inspection of the
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licensee's controls over scheduled surveillances revealed no discrepancies.
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(Open) Outstanding Item (Details I, paragraph ll.d of RII
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Rpt. 77-17) Diesel Generator Annunciators.
MAR 77-7-33 has been completed but post-modification test information was unavailable and the MAR had not completed PRC review.
e.
(Closed)
Outstanding Item (Details I, paragraph 5 of RII Rpt.
77-17), Compliance Section Audits.
These audits have been resumed and the inspector reviewed the schedule of first and second quarter 1978 audits and completed audits 78-2 and 78-3.
No discrepancies were identified.
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f RII Rpt. No. 50-302/78-10 I-3 (v/
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(Closed) Outstanding Item (Details I, paragraph 5 of RII Rpt.
77-17), Identification of Alternates in PRC Minutes. The inspector reviewed minutes from PRC meetings 78-9, 78-10, and 78-11 to determine this is being accomplished.
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(Closed) Unresolved Item (Details I, paragraph 6 of RII Rpt.
77-18), Jumper Controls. The licensee has reviewed all outstanding jumpers to assure requirements of Technical Specification 6.5.1.6(d) and 10 CFR 50.59 concerning safety evaluations are met.
4.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance, or deviations. Two unresolved items (Decontamination Cleaner - 78-10-02, and Decontamination Procedures - 78-10-03) were identified and are discussed in paragraph 13.
5.
Exit Interview A meeting was held by R. H. Wessman with G. P. Beatty, Jr. and members of his staff on April 28, 1978.
Items covered by the
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O inspecticn were discussed. The noncompliance item relating to the late submittal of the March Monthly Operating Report was discussed with the licensee by telephone May 1, 1978.
6.
Submittal of the Monthly Operating Report The licensee advised the inspector that due to an administrative oversight the March 1978 Monthly Operating Report was not transmitted within the time required by Technical Specifications.
Technical Specification 6.9.1.6 requires that routine reports of operating statistics and shutdown experience be submitted on a monthly basis not later than the 15th of the month following the calender month covered by the report.
Contrary to this Technical Specification, the March 1978 Monthly Operating Report was not submitted until April 25, 1978.
This has been identified as a deficiency in the Notice of Violation.
(78-10-01)
7.
Review of Fuel Inspection Activities and Retrieval of Parts of the Broken Burnable Poison Rods The inspector reviewed procedures and selected data taken during inspection of the Crystal River 3 fuel assemblies and retrieval of parts of the broken burnable poison rods (BPRA). The following 7~
aspects of that activity were reviewed:
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RII Rpt. No. 50-302/78-10 I-4
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Complete fuel assembly inspection data for assemblies
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3C35 and 3C37 (which had contained the failed burnable poison rods).
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Guide tube integrity test records on fuel assemblies 3C35
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and 3C37.
Inspection records for all fuel assemblies (documentation
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generated duting core unloading).
Records of " debris removal" for fuel assemblies identified
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as having pieces of the broken burnable poison rods in the lower end fittings.
Records for removal and inspection of other Burnable Poison
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Rod Assemblies. All BPRA's have been removed.
Records of inspection of fuel assemblies upper end fittings
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and latch tubes for wear induced by BPRA's or orifice rod assemblies.
(No wear induced by orifice rods was identified by the licensee. Various fuel assemblies had minor upper end O
fitting wear induced by the BPRA's)
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Records for orifice rod assembly inspection.
(No evidence
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of wear or loss of ball-locks was identified.)
The inspector has not reviewed inspection procedures and records for reactor vessel, core support assembly or plenum assembly inspection as this work had not been completed at the time of the inspection.
The inspector stated his intent to review this data, and any other procedures / data relating to the fuel assemblies and core reload, prior to initiation of core reloading (78-10-04).
8.
Review of Logs and Short Term Instructions The inspector reviewed selected plant logs and short term instructions for the January-April 1978 period. These documents were reviewed for consistency with the requirements of Technical Specification 6.10.1 and the procedural guidance of A.I. 500, Conduct of operations.
Documents reviewed included:
Control Room Nuclear Operators Log - March 22, 1978 -
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April 24, 1978 Shift Supervisor's Log - April 4, 1978 - April 10, 1978
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and April 23, 1978 - April 27, 1978 s
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RII Rpt. No. 50-302/78-10 I-5 SP 301, Shutdown Daily Surveillance Log - April 2, 1978 -
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April 18, 1976
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Short Term Instructions currently in effect on April 29, 1978
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The inspector determined that log reviews were being conducted by appropriate members of the plant staff and that log entries were consistent with Technical Specification limits.
No discrepancies were identified.
9.
Facility Tours and Observation of Control Room Activities The inspector toured various areas of the Crystal River 3 facility to observe plant outage activities in progress, and to ascertain the general state of cleanliness and housekeeping.
The inspector
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observed portions of plant activities on a daily basis that included all three shifts.
The ing7ector observed portions of control room activities at various timte during the inspection.
The inspector interviewed operations watchstanders, reviewed selected portions of logs and plant instrumentation, and verified compliance with Technical Specifications requirements.
Inspector observations on the following were conveyed to licensee representatives *
I a.
Snubber RCH-90 in the reactor building was found with low oil.
The licensee initiated appropriate documentation to track and rectify this discrepancy.
b.
Much of the low level solid waste that was awaiting drumming (Details I, paragraph 7 of RII Rpt. 78-6) has been drummed.
c.
Miscellaneous comments of a minor nature.
10.
Control of Plant Clearances The inspector reviewed the licensee's program for the control of in-plant clearances. The program was reviewed for compliance with CP-ll5 (In-Plant Clearance and Switching Orders) and the requirements of Technical Specification 6.8.1.
The Clearance Log and randomly selected individual clearance control sheets for January-April 1978 wers reviewed.
The inspector verified by direct observations the placement of tags for eight clearances.
The inspector and the licensee discussed Clearance 04-213 issued April 25, 1978, for the Decay Heat Pump 1A repair. The plant manipulations required by this clearance were approved by the Plant Review Committee as required by CP-115.
However, the manipulations
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are of a standard and repetitive nature, and are appropriate for inclusion in the system operation procedure.
The licensee committed to revise OP-404, Decay Heat Removal System, by June 30, 1978, to include steps to remove / return a decay heat pump from/to service
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and to remove / return a decay heat cooler from/to service.
11. Review of Control Room Jumper Log The inspector reviewed the licensee's program for control of temporary modifications and jumpers for consistency with the requirements of the Technical Specifications and 10 CFR 50.59.
As part of that review, the inspector examined CP-ll4, Procedure for Control of Permanent Modifications, Temporary Modifications, and Deviations; and reviewed the Jumper and Lifted Wire Log maintained in the control room.
The Unresolved Item relating to jumpers was closed as part of this review (see paragraph 3.r; of these details). The
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inspector also verified by direct observation the placement of tags t
for five jumpers / lifted leads.
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Several discrepancies of a minor natura, were discussed with the licensee and will be reviewed on a subsequent inspection (78-10-05).
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These descrepancies included.
.l The copy of CP-ll4 in the front of the Jumper Log notebook
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was revision 9 vice the current revision 11.
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Several non-safety-related jumper forms were incorrectly filled out.
Several jumpers were still installed several months after
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the " expected removal date".
The licensee acknowledged the inspectors comments and agreed to consider a compliance section review of the jumper log.
12.
Review of Nonconferming Operations Reports The inspector reviewed approximately 80 Nonconforming Operations
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Reports (NCOR's) generated during the January-March 1978 period.
These NCOR's were reviewed for consistency with the requirements of the Plsnt Technical Specifications and CP-lll, Procedure for Documenting the Reporting and Review of Nonconforming Operations.
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Several NCOR's reviewed. pertained to radiation monitor alarma.
Review of supporting data confirmed that no technical specification limits were violated. The inspector determined that licensee procedures for analysis of gaseous release samples don't assure
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analysis for conformance to 10 CFR 20.403 limits.
The licensee has agreed to. revise the cppropriate analytical procedures accordingly
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by July 1, 1978 (78-10-06).
Various inspector questions concerning NCOR's were resolved in
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discussions with the licensee.
No discrepancies were identified.
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I 13. Decontamination of Reactor Coolant System or RCS - Pressure Boundary Components In response to an Office of Nuclear Reactor Regulation request, the inspector inspected Crystal River 3 activiries to verify that
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adequate steps have been taken to prevent the uncontrolled intro-duction of decontamination solutions or their residues into compo-nents within the RCS-pressure boundary.
The inspector determined that no chemical decontamination on RCS pressure boundary components has been conducted, or is planned, at Crystal River 3 with the exception of a chemical deconta=ination done on RCV-8 (Pressuri:er Code Relief) as part of a recent maintenance activity.
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RCV-8 was cleane?. in the ultrasonic sink using a chemical identified
as NT-600EL Decontaminating Cleaner, manufactured by Nuclear Technology
Corporation and distributed by Todd Research and Development Corporation.
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No analysis of this cleaner, nor certification papers were available to assure its compatibility with RCS-pressure boundary components.
I The uncertainty as to the acceptability of NT-600EL Decontaminating Cleaner for nuclear use is designated as an Unresolved Item (78-10-02).
The inspector reviewed the licensee's controls over decontamination activities.
Procecures reviewed were:
OP-420, Sonic Decontamination
Equipment Operations, and CP-ll6, Standard Cleanliness Specifications.
These procedures are silent concerning:
a.
Decontamination procedures to be used (as opposed to Decontamination equipment operation procedures provided in OP-420).
b.
Identification of approved cleaning solutions for decontamination evolutions.
c.
Requirements to consider the possibility of a 10 CFR 50.59 safety evaluation being appropriate for decontamination activities involving RCS pressure boundary components.
The foregoing three items concerning decontamination procedures will be identified as an Unresolved Item (78-10-03).
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14.
LER 78-019/01T, Possible Error in Small Break Analysis
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The inspector reviewed LER 78-019 regarding a possible error in the Babcock and Wilcox anrlysis of a postulated small break to the
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reactor coolant system. The re-analysis by B&W is not complete and corrective actions have not yet been formulated.
The licensee
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stated that corrective actions will be addressed prior to restart of Crystal River 3 from the current outage.
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