IR 05000302/1979034
| ML19254F172 | |
| Person / Time | |
|---|---|
| Site: | Crystal River |
| Issue date: | 09/26/1979 |
| From: | Dance H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19254F171 | List: |
| References | |
| 50-302-79-34, NUDOCS 7911070243 | |
| Download: ML19254F172 (4) | |
Text
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UNITED STATES
NUCLEAR REGULATORY COMMISSION o
$
E REGION 11
o 101 MARIETTA ST N.W SUITE 3100 o
ATLANTA, GEORGIA 30303
.....
Report No. 50-302/79-34 Licensee: Florida Power Corporation 3201 34th Street, South St. Petersburg, Florida 33733 Facility Name:
Crystal River #3 Docket No. 50-302 License No. DPR-72 Inspected at Crystal River 3 Inspected by:
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6 79 G. A. Belisle
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Date Signed
!20 Approved by:
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H. C; Dance, Section Chief, RONS Branch Date Signed SUMMARY Inspected on August 27-31, 1979.
Areas Inspected This reutine, unannounced inspection involved 36 inspector-hours onsite in the areas of outage maintenance activities related to reactor coolant pump seal replacement and feedwater system testing, and review of operating procedures and drawings.
Results Of the 2 areas inspected, no apparent items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees
- G. Beatty, Nuclear Plant Manager
- P. McKee, Operatior x perintendent
- J. Cooper, Compliar.e.- Engineer
- G. Ruszala, Radwaste Supe 7isor
- L. Hill, Compliance Audiwr
- J. Wright, Chem-Rad Protection Engineer
- J. Harrison, Assistant Chem-Rad Protection Engineer
- T. Lutkehaus, Support Engineer
- W. Cross, Operations Engineer
- W. Kemper II, Nuclear Technical Specification Coordinator
- G. Williams, Nuclear Compliance Plant Engineer
- S. Ewald, U.S.N.R.C.
G. Westafer, Maintenance Superintendent F. Pleubel, Electrical Supervior D. Breedlove, Document Control Other licensee employees contacted included 2 technicians, 6 operators, and 4 office personnel.
Other Organizations J. Marsh, Babcock & Wilcox
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarizeu on August 31, 1979, with those persons indicated in Paragraph I above.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve noncompliance or deviations.
New unresolved items identified during this inspection are
- discussed in paragraph 6.
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5.
Outage Maintenance Activities Reactor Coolant Pump IC Seal Replacement a.
The inspector reviewed Maintenance Procedure 115, RC Pump Inspection and Replacement, and seven work request (08701, 08702, 08326, 08617, 08630, 08362 and 08657) pertaining to the replacement of reactor coolant pump IC seal. During the review of Maintenance Procedure 115 several questions arose pertaining to quality control hold point signatures.
These questions were resolved by talking to cognizant quality control personnel.
No items of noncompliance or deviation were identified.
b.
Feedwater System Testing The inspector met with cognizant licensee personnel as well as a representative of Babcox & Wilcox to review the work accomplished to the feedwater system.
The inspector was informed that all of the feedwater system electronic modular components had been fuctionally checked for proper operation. A review of existing records, however, showed that a total of nineteen modules had not been functionally verified. The licensee did perform a functional check of the nineteen modules in question. During the functional check one module 4-10-1 found to have an excessive gain setting. This gain setting was was readjusted at the direction of the Babcox & Wilcox representative.
The inspector reviewed work requests 8736, 10182, 04950, 04951, 04953, and 10242 for additional work that was done on calibration of feed-water system components.
The inspector was informed of a lockup problem that was found when stroking the feedwater start up valves, FWV 39 and FWV 40, under certain conditions. The inspector reviewed MAR 79-4-3 and work request 08753, for the installation of one half inch tubing from the air supply to FWV 39 and and FWV 40, to prevent recurrence of this problem.
Work on installation of this tubing was in progress.
No discrepancies were identified.
6.
Inadvertent ES Actuation On August 26, 1979, while changing inverters to redundant power supplies,an engineering safeguards activation occurred. The licensee submitted a Non-conforming Operation Report (NCOR 79-326) and had appointed cognizant plant
, personnel to review the cause of the incident. Until such time as this review is completed, and corrective action taken to prevent recurrence this item remains unresolved (79-32-01).
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7.
Damaged Relay in Relay Rack 3 On August 29, 1979, at approximately 1:40 p.m., a relay, in relay Rack 3, was observed to be emitting heavy smoke. The fire alarm wa.s sounded and the licensees' actions during the emergency were observed. The relay was quickly deenergized and no major problems were encountered. The inspector reviewed the licensees' procedural controls for handling the fire emergency to verify that the actions specified were taken.
No items of noncompliance or deviation were identified.
8.
Review of Operating Procedures and Drawings The inspector reviewed the following operating procedures and drawings for selected safety systems to verify system alignment was specified: OP 401 Core Flooding System, OP 402 Purification and Makeup System, OP 404 Decay Heat Removal System, OP 405 Reactor Building Spray System, OP 605 Feedwater System, No items of noncompliance or deviations were identified.
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