IR 05000302/1977017
| ML19317G167 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 11/01/1977 |
| From: | Dance H, Wessman R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19317G158 | List: |
| References | |
| 50-302-77-17, NUDOCS 8002280770 | |
| Download: ML19317G167 (9) | |
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Report No.: 50-302/77-17 Docket No.: 50-302 License No.: DPR-72 Licensee:
Florida Power Corporation 3201 34th Street, South P. O. Box 14042 St. Petersburg, Florida 33733 Facility Na -: Crystal River 3 Inspection at: Crystal River Site, Crystal River, Florida Inspection conducted: September 20-23, 1977
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Inspector:
R. H. Wessa Reviewed by:
C kN n !' !"2 7 H. C. Dance, Chief bate Reactor Projects Section No.1 Reactor Operations and Nuclear Support Branch Inspection Summary Inspection on September 20-23, 1977 (Report No. 50-302/77-17)
Areas Inspected: Routine unannounced inspection to followup on Licensee Reportable Events; followup on IE Circulars; and to conduct a facility tour. The inspection involved 26 inspector-hours on site by one.NRC inspector.
Results: Of the three areas inspected, two items of noncompliance were identified in one area (Deficiency - failure to meet reporting requirements - Details I, paragraph 5; Deficiency - failure to follow alarm response procedures - Details I, paragraph 6).
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RII Rpt. No. 50-302/77-17 I-1
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E N.Ju e O4 b7 DETAILS I Prepared by:
i R. H. Wessman, Reactor Inspector Date Reactor Projects Section No.1 Reactor Operations and Nuclear Support Branch Dates of Inspection: September 20-23, 1977 Reviewed by:
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H. C. Dance, Chief Date Reactor Projects Section No.1 Reactor Operations and Nuclear Support Branch
5 1.
Persons Contacted
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Florida Power Corporation (FPC)
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- G.
P. Beatty, Jr., Nuclear Plant Manager
- W.
R. Nichols, Operations Supervisor
- P. F.'Mckee, Assistant Nuclear Plant Manager
- G. F. Westafer, Technical Support Engineer
- J. R. Wright, Chemical / Radiation Protection Engineer
- J.
Cooper, Compliance Auditor
- C.
G. Goering, Compliance Auditor
G. L. Clarr, Compliance Auditor
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F. W. Pluebells Electrical Supervisor
- Denotes those present at the exit interview.
2.
Licensee Action on Previous Inspection Findings Not inspected.
3.
Unresolved Items No new unresolved items.
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4.
Exit Interview A meeting was held by R. H. Wessman with % P. Beatty, Jr. on September 23, 1977. Items discussed included the noncompliance j
items (paragraphs 5 and 6 of these details) and other areas
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inspected. The licensee was also informed that R. H. Wessman would be the Principal NRC Inspector for this facility.
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RII Rpt. No. 50-302/77-17 I-2
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5.
Failure to Meet Reporting Requirements The inspector reviewed portions of LER 77-103E concerning an unplanned
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release that occurred on September 3, 1977. At 0716 on that date, while venting t s makeup tank to the low pressure waste gas header, h
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the loop seal es the miscellaneous waste evaporator was blown t
allowing a reb u.
This event is reportable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.of
- r ed by Environmental Technical Specification occurrence at. r
5.6.2.A.
Con'. t this Technical Specification, the NRC Region II intil 1200 on September 4, 1977.
This Office was not a
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i noncompliance iten ia..ousidered a deficiency.
l 6.
Failure to Follow Alarm Response Procedures The inspector reviewed with the licensee the circumstances relating to an unmonitored gas release that occurred on September 18, 1977,
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during the conduct of a Reactor Building purge.
(This release was l
reported to the NRC as Licensee Event Report 77-ll6E). As required-
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by Technical Specifications, releases made during the conduct of a reactor building purge are monitored continuously by detector RM-A1.
The licensee's procedure AP-103, Radiation Monitoring System Alarms, provides operator actions in the event of a monitoring i
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system failure. In accordance with Section 2.0 of AP-103, the operator is required to immediately terminate the reactor building purge in the event of a failure of RM-A1.
At 0509 on September 18, 1977, while in the progress of conducting a reactor building purge, a RM-Al hi/ low flow alarm was received in j
the control room and recorded on the alarm typer.
This alarm is
indicative of a failure of RM-A1.
The reactor building purge was
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not terminated until 0800 on that date. This action is contrary to Technical Specification 6.8.1 which requires that ".. written j
procedures shall be established, implemented, and maintained..."
l This noncompliance f:em is considered a deficiency.
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l 7.
Review of Licensee Event Reports (LER's) Related to Surveillance
Actions The inspector reviewed various LER's related to surveillance actions
to confirm licensee analyses of the occurrences and determine i
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implementation of corrective actions. The follow 1ng LER's were
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reviewed and closed:
77-42 - Missed ES System Surveillance
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77-58 - Missed Surveillance on Motor-Driven Emergency Feed Pump
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RII Rpt. No. 50-302/77-17 I-3
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77-66 - Missed Nuclear Services Closed Cycle Cooling System Surveillance 77-68 - Missed I-131 Surveillance after Reactor Trip
77-82 - Missed Radiation Monitor Surveillance 77-84 - Failure to Enter Action Statement as a Result of a Battery Surveillance i
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77-98 - Missed RPS Channel "A" Surveillance The inspector reviewed the licensee's program for control of surveil-lance activities and changes made as a result of these LER's.
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j following prograss.atic aspects are noted:
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a.
Several surveillance actions were missed due to scheduled I
revisions to incorporate surveillance requirements of Section XI of the ASME Boiler and Pressure Vessel Code. The schedule has been reviewed to incorporate omissions.
b.
Several Surveillance actions were affected oy changes to the master surveillance schedule. The schedsie has been revised
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I to incorporate omissions.
c.
A compliance auditor has been charged with daily monitoring of surveillance activities.
a d.
The licensee's program to assure execution of "special situation" surveillances (those surveillances triggered by a change in a
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plant parameter or mode change) is under review.
e.
The inspector clarified LER entries concerning the " failure data" and violation code.
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8.
Review of Licensee Event Reports (LER's) Related To Plant Cooldown Rates
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The inspector reviewed two LER's related to occurrences of an excess cooldown rate to confirm licensee analyses of the occurrences
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'and determine implementation of corrective actions. The following LER's were reviewed:
77-20 Excess Cooldown After Loss of Power to the
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Integrated Control System (Closed in IE Report
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50-302/77-6)-
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RII Rpt. No. !")-302/77-17 I-4
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77-29 Exeass Cooldown During RCS Shutdown From Outside
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Control The inspector verified equipment maintenance recoras and confirmed procedure revisions to EP-113 (Plant Shutdown From Outside Control)
and OP-209 (Plant Cooldown) generated as a result of LER 77-29.
This LER is closed.
9.
Review of Licensee Event Reports (LER's) Related to Meeting ACTION Statements The inspector reviewed two LER's related to meeting Technical Specification ACTION statements to confirm licensee analyses of the occurrences and determine implementation of corrective actions.
l The following LER's were reviewed and closed:
77-62 Exceeded 8-Hour Limit to Be Below 60% Power Upon
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Loss of Absolute Rod Position Indication 77-100 Exceeded ib Hour Limit to Be at Hot Shutdown Upon
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Core Flood Tank Inoperability LER-77-62 corrective action was implemented via instructions given to operations personnel by the' Operations Supervisor.LER 77-100 corrective action committed to the issue.of a graph of conservative attainable cooldown rate by October 1, 1977. This graph has been m ued and was reviewed by the inspector.
10. Review of Licensee Event Reports (LER's) Related to The Reactor
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i Building Purge Monitor
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The inspector reviewed various LER's related to difficulties with the reactor building purge monitor to confirm licensee analyses of i
the occurrences and determine implementation of corrective actions.
The following LER's were reviewed:
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77-27 RM-Al Vacuum Pump Inoperable
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77-74 - RM-Al Inoperable During Reactor Building Purge (Closed in IE Rcport 50-302/77-14)
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77-105E - Commenced Reactor Building Purge with RM-Al Incperative
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77-116E - Conducted Reactor Building Purge with RM-Al inoperative f
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RII Rpt. No. 50-302/77-17 I-5
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LER's 77-27,105E, and 116E remain open pending further NRC review and implementation of licensee corrective actions. The following consnents apply:
a.
The corrective action for LER 77-27 stated that a request is to be initiated to bring Appendix A Technical Specifications in conformance with Appendix B.
This request for a Technical Specifications change has not been received by the NRC, according to Region II records.
b.
The changes to the reactor bufiding purge section of OP-417,
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Containment Operating Procedure, as constitted in the Corrective Action of LER 77-74E, were verified by the inspector. However a similar change to the containment equalization section of OP-417 had not been made. The licensee committed to implement j
this change by October 15, 1977.
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c.
The licensee has generated an engineering design chs.nge request
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to trip the reactor building purge upon failure of f;he building purge monitor (RM-A1). This change is under corporate office i
review.
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11.
Review of Licensee Event Reports (LER's)
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The inspector reviewed various LER's to confirm licensee analyses of the occurrences and deterndne implementation of corrective actions. LER's were reviewed and inspection activities are summarized
as follows:
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LER 77-77, Chemical Addition Pumps Inoperable The inspector reviewed Work Request 3612 and verified installa-tion of the pump vent valves. This LER is closed, b.
LER 77-85, Reactor Buildina Charcoal Filter Efficiency Low l
The inspector verified the documentation ge.2erated cont.orning the replacement filter installation and retest executed on August 11, 1977. This LER is closed.
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c.
LER 77-86, Battery Specific Gravity Low This LER is closed without comment.
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RII Rpt. No. 50-302/77-17 ~
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d.
LER 77-94, 3B Emergency Diesel Generator Failed to Start
The inspector reviewed a procedural change to SP-354, Emergency Diesel Fuel Oil Quality and Diesel Generator Monthly Test,
which calls for a reset of local diesel trips. -Also confirmed was the status of Plant Modification MAR 77-7-33.
This modifi-cation, currently in engineering review, will provide control room annunciation of the inability of the diesel generators to perform any parameter of the starting sequence. This LER is closed.
e.
LER 77-97, High Pressure Injection Valve (MUV-25) Inoperative The inspector reviewed the licensee's program for corrective action. The licensee is checking all ES valve motor control
centers for mechanical binding of the reversing interlocks in
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a manner similar to that reported in this LER. Additionally
these interlocks are being cleaned, adjusted, at.d lubricated I
as necessary. The licensee has completed about 1/3 of the approximately 100 valve motor control centers scheduled for'
inspection. This LER is closed, f.
LER 77-99, Exceeded Primary Containment Average Air Temperature This LER occurred as a result of an it.lustrial cooling water i
supply valve being left closed. The inspector reviewed a i
procedural change to SP-344, Nuclear Service Cooling Water i
System Operability, which ensures that upon completion of SP-
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344 the cooling water supply valves will be verified in the open position. This LER is closed.
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LER 77-107E, Gas Release From Makeup Tank During Hydrogen Header Maintenance The inspector reviewed the work request, clearances, and maintenance controls relating to the hydrogen header maintenance action. This LER remains open pending NRC review of the health physics aspects of the event.
h.
LER 77-104, Four RCS Flow Instruments Exceeded Calibration Tolerances
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The inspector reviewed calibration data sheets for the differen-tial pressure transmitters associated with this LER. This LER is closed.'
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12.
Facility Tours The inspector toured portions of the Crystal River 3 facility daily -
between the dates of September 20 and September 23, inclusive. The inspector noted various housekeeping and cleanliness items to licensee representatives, includir.s the following:
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Compared to other recently licensed facilities, Crystal River
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has a large number of areas for which surface contamination requires specific health physics controls.
Compared to other recently licensed facilities, Crystal River
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has many minor water leaks in auxiliary systems.
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Cleanup is not always executed immediately after some maintenance actions (examples are: entry room on 119-foot level outside containment access door, weld repair on decay heat closed cycle cooler, gage replacement on waste transfer pumps).
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Although most auxiliary building hallways, rooms, and galleries arc clean, numerous chips and worn spots in floor paint allow V
any spilled contamhated liquids to soak into the concrete.
13.
Review of IE Circulars The inspector reviewed applicable IE Circulars with licensee personnel to ascertain that they had been received on site and reviewed by cognizant supervisory personnel. The following IE Circulars have been received by Crystal Rivnr 3:
Circular No.
Subj ect 77-01 Malfunctions of Limitorque Valve Operators 77 '3 Fire Inside a Motor Control oenter 77-C'+
Inadequate Lock Assemblies 77-05 Liquid Entrapment in Valve Bonnets 77-06 Effects of Hydraulic Fluid on Electrical Cable b
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RII Rpt. No. 50-302/77-17 I-8
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77-08 Failure of Feedwater Sample Probe 77-10 Vacuum Conditions Resulting in Damage to Liquid Process
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Tanks (IE Circulars 77-02, 77-07, and 77-69 are not applicable to Crystal River). The inspector suggested that IE Circulars be given appro-priate supervisory routing (even if not applicable to an individuals discipline).as an aide in professional development.
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