IR 05000302/1976024
| ML19308D286 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/28/1976 |
| From: | Jape F, Robert Lewis, Rogers R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19308D268 | List: |
| References | |
| 50-302-76-24, NUDOCS 8002270732 | |
| Download: ML19308D286 (13) | |
Text
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UNITED 5TATES NUCLEAR REGULATORY COMMISSION
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230 PEACHTREE STREET, N.W.SulTE 818
ATLANTA,GLORGIA 30303
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f IE Inspection Report No. 50-302/76-24
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Licensee: Florida Power Corporation 3201 34th Street, South
P. O. Box 14042
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St. Petersburg, Florida 33733
I Facility Name: Crystal River 3 Docket No.:
50-302
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License No.:
DPR-72 Category:
B2 Location: Crystal River, Florida Type of License:
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Type of Inspection: Routine, Announced (December 4-6, 1976)
Routine, Unannounced (December 6-9, 1976).
Dates of Inspection: December 4 9, 1976 Dates of Previous In:'ection: November 17-19, 1976
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Principal Inspector:
I, Jape, Reactor Inspector Reactor Projects Section No. 2
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Reactor Operations and Nuclear Support Branch i
l (December 6-9, 1976)
i Accompanying Inspectors:
R. F. Rogers, Reactor Inspector l
Reactor Projects Section No. 2 j
Reactor Operations and Nuclear Support Branch (December 4-9, 1976)
j G. L. Troup, Radiation Inspector Radiation Support Section
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l Fuel Facility and Materials Safety Branch
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(December 7-9, 1976)
I 0ther Accompanying Personnel: None
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IE Rpt. No. 50-302/76-24-2-
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/2[2/!70 Principal Inspector:
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F. Jape, Reacto 6 Inspector Date
Reactor Projects Section No. 2 l
Reactor Operations and Nuclear " Support Branch Reviewed by:
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C.' Lewis, Chief date'
Reactor Projects Section No. 2
l Reactor Operations and Nuclear Support Branch
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IE Rpt. No. 50-302/76-24-3-I
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SUMM*.RY OF FINDINGS
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I.
Enforcement Matters
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None
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II.
Licensee Action on Previously Identified Enforcement Matters
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Not inspected.
III. New Unresolved Items 76-24/1 Facility Records Record retention program is not in complete agreement.
with requirement of Technical Specification 6.10.
i (Details I, paragraph 5)
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76-24/2 Inservice Surveillance Program
Inservice surveillance program is not based on require-ments of Technical Specification 4.0.5.
(Details I, paragraph 6)
IV.
Status of Previously Identified Unresolved Items 75-19/4 Testing of Sample Lines
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Testing of the sample lines has been completed with j
acceptable results. The test procedure has been reviewed
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and approved by the licensee. This item is closed.
(Details III, paragraph 2)
75-19/6 Sample Media collection Efficiencies The air sampler modification has not been made to in-crease the residence time and provide acceptable collac-tion efficf.encies for the adsorbers. This item remains
open.
(Det. ails.III, paragraph 3)
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Unuaual Occurrences
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IE Rpt. No. 50-302/76-24-4-
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VI.
Other Significant Findings
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A.-
Facili~.y Operating License Facility operating license DPR-72 was issued December 3, 1976,
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permitting the facility to be in cold shutdown mode 5 and re-
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fueli4 ade 6.
B.
Initial Fuel Loading
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Initial fuel loading began on December 4, 1976, and was com-plated December 9, 1976. Fuel loading operations required approximately 93 hours0.00108 days <br />0.0258 hours <br />1.537698e-4 weeks <br />3.53865e-5 months <br /> to complete.
C.
Chemistry Fume Hoods
Licensee's response, dated December 13, 1976, to the deviation concerning performance of the chemical fume hoods has been
reviewed'. Satisfactory performance har, been verified. Item
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is closed. (Details III, paragraph 4'
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VII. Management Interview A management interview was held on December 9, 1976, with G. P. Beatty, Jr. and members of his staff. The inspection findings were discussed, which included the initial fuel _ loading
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activities. Items requiring resolution prior to inftial criti-cality were reviewed.
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IE Rpt. No. 50-302/76-24-I-1 1-
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DETAILS I Prepared by:
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F. Jape, Reactor Inspector Date-Reactor Projects Section No. 2
Reactor Operations and Nuclear Support Branch Dates of Inspection: December 6-9, 1976 Reviewed by:
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R. C. Lewis, Chief
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Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch
1.
Individuals Contacted Florida Power Corporation (FPC)
J. Alberdi - Project Manager G. P. Beatty, Jr. - Nuclear Plant Superintendent J. C. Hobbs, Jr. - Manager Generation Testing B. Chastain - Administrative Manager D. W. Pedrick, IV - Compliance Engineer H. B. Lucas - Administrative Supervisor J. E. Barrett - Plant Engineer H. E. Reeder'- Nuclear-Shift-Supervisos
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E. E. Froats - Manager, Site Surveillance 2.
Status of Facility Completion Followup on the status of facility completion was continued during
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this inspection. The master punch list, maintained by the licensee, and other records were examined to determine the status of preopera-tional testing and construction activity. In summary, five preopera-
,tional tests require resolution prior to initial criticality.
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These are summarized below:
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a.
TP 150-3 - Post Accident H Purge Test - Purge rate not within
the acceptance criteria presented in the test procedure.
Licensee is reevaluating the test results and has stated that j
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a revision to the acceptance criteria is being considered to resolve this. item.
b.
TP 600-36 - Reactor Building Cooling - A retest to resolve a fan balance deficiency 1 scheduled'to be performed during
. plant heatup.
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TP 160-7 - Reactor Cavity Cooling - A retest during plant j
heatup is scheduled to obtain additional test data.
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TP 267-5 - CRD Cooling Functional - A retest during plant heatup is sched tied to balance flow.
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TP 302-2 and 3 - lucore System '- Repair of cable connectors has been completed. Testing of cables and connectors is aj currently underway.
Followup on these items will be conducted on subsequent inspections.
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3.
Hydraulic Snubber Siaht Glass Leakage
l In inspection report 50-302/76-22, the repair status of leaky sight
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glasses on hydraulic snubbers was discussed. Followup on this item
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revealed that all snubbers in 'the reactor building have been repaired and 22 snubbers in the auri11ary building remain to be repaired.
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Licenses astimates the repairs will be completed by December 15,
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1976. Followup will be conducted on subsequent inspections.
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4.
Fuel Inspection i
The licensee's program for inspecting fuel prior to fuel loading was reviewed. The fuel was inspected at the time of receipt using FP-302 " Fresh Fuel Receipt, Inspection, Inventory, Documentation and Storage." The inspection records for twenty fuel assemblies were reviewed. No discrepancies were identified.
- Each fuel assembly was also aramined during fuel loading operations as it was removed from its storage rack. A visual aramination was
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l conducted by the fuel handling bridge operators and their findings were documented in the initial fuel loading procedure. This activity was observed by the inspector f'r two fuel assemblies during fuel o
loading and a review of the inspection record revealed that all
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fuel,was acceptable. There were no discrepancies identified.
i 5.
Facility Records
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The licensee's program for control and retention of records was i
reviewed using Section 12.5 of the FSAR and Technical Specification 6.10 as.. guidance. The licensee's program is delineated in Document Control Procedure DC-101, " Drawing and Document Control." A review of this procedure revealed that it did not address retention of all records required by Technical Specifications 6.10.1 and 6.10.2.
The discovery that DC-101 is not in complete agreement with require-
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IE Rpt. No. 50-302/76-24
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munts was identified as unresolyc' item 76-24/1. Licensee management
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stated that the item would be reviev.2 and the procedure revised
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appropriately.
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Other parts of the records program that were reviewed, were found to be satisfactory. These incitJed such items as designation of custodians, filing and retrieval methods and accountability of records removed from storage.
6.
Inservice Surveillance Program i
The licensee's inservice surveillance program was avamined using Technical Specification 4.0.5 as guidance. At the present time, the licensee's program is based on the March 30, 1976, version of the Technical Specifications (TS) rather than on the final Technical Specifications. During the inspection it was not determined whether i
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TS 4.0.5 was being met or not. FPC has requested written relief from the requirements of TS 4.0.5 for the initial period of opera-tion in order to rewrite the inservice program as required by TS 4.0.5.
At the time of the inspection, written relief had not been granted by Reactor Licensing.
This inconclusive finding was identified as unresolved item 76-24/2. Followup on this item will be conducted on future inspections.
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IE Rpt. No. 50-302/76-24 II-1 r. !< r. lo
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DETAILS ~II Prepared by:
-u R. F. Rogers, III, Reactor Inspector Date
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Reactor Projects Section No. 2
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Reactor Operations and Nuclear Support Branch
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Dates of Inspection: December 4-9, 1976 Reviewed by:
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R. C. Lewis, Chief
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Date'
Reactor Projects Section No. 2
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Reactor Operations and Nuclear Support Branch 1.
Personnel Contacted J. Alberdi - Project Manager G. P. Beatty, Jr. - Nuclear Plant Superintendent J. R. Wright - Checistry and Radiation Protection Engineer D. W. Pedrick, IV - Compliance Engineer W. R. Klein - Reactor Engineer J. C. Hobbs, Jr. - Manager, Generation Testing
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G. D. Perkins - Health Physics Supervisor i
E. E. Froats - Manager, Site Surveillance 2.
Initial Fuel Loading
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The inspector witne.
<.d the initial fuel loading of the reactor.
The first fuel element was seated in the reactor vessel at approxi-mately 0220 on December 4, 1976. The complete loading sequence required 4 days (93 hours0.00108 days <br />0.0258 hours <br />1.537698e-4 weeks <br />3.53865e-5 months <br />). The licensees actions were evaluated against the requirements of Regulatory Guide 1.68, Appendix C Section B, " Fuel Loading," FSAR Section 13.4.5, " Initial Reactor Fuel Loading," and Technical Specifications Section 3/4, " Limiting Conditions for Operation and Surveillance Requirements." The adequacy of operating staff performance and their compliance with the approved procedure FP 202, " Initial Fuel Loading" was also inspected. The inspector observed shift turnovers, record keeping,
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data collection techniques, overall supervisory control, and ra'io-d logical control techniques. The evolution was. conducted within the requirements of the facility license.
3.
Quality Assurance for the Startup Test Program The licensee's program for quality assurance auditing during the power ascension test program was reviewed. Procedures have been
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IE Rpt. No. 50-302/76-24 II-2
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established for conducting the program, documenting test results, and tracking deficiencies. The corporate QA group will audit completed test procedures on a random basis. The Plant Review Committee (PRC) will review all test results. The documentation, resolution, correction, and retest of selected deficiencies and specific QA audit results will be inspected during the startup test program.
4.
Technical Specification Compliance A review of technical specification requirements applicable to the fuel loading was performed. Control room indications of plant
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parameters and randomly selected records were inspec'id to verify compliance with the limiting conditions for operations in the operating license. Requirements relative to the fuel loading in progress received emphasis. No discrepancias were noted.
i 5.
Review of Containment Integrated Leak Rate Test Results The inspector reviewed the results of the preoperational containment integrated leak rate test (CILRT) conducted on November 3-6, 1976.
The results of test procedure TP 71'150 2, " Initial Reactor Building Integrated Leak Rate Test" and Gilbert Associates (GAI) Report No. 1927 "Preoperational Integrated Leak Rate Test of the Reactor Containment Building" were compared with the actual results observed by the NRC inspector during the test. The documented results and
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,,, conclusions _were within established __accepgance er.i.teria._
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Review of Structural Integrity Test (SIT) Results l
The inspector reviewed the results of the structural integrity test contained in GAI. Report No. 1930, " Reactor Containment Building Structural Integrity Test," and had no questions.
7.
Power Ascension Procedures Verification The scope of the power ascension test program was reviewed. During Inspection Report No. 50-302/76-7, an open item was identified in i
that the part-length rod tests required' by RG 1.68, Appendix A,
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Section D.1.M. were not scheduled for completion. This modification of the test program has been accepted by the NRC. This item is closed.'
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IE Rpt. No. 50-302/76-24 III-1
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DETAIIS III Prepared by:
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/R[#Pb/s y G. L. Troup, Radiation Specialist Date
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v Radiation Support Section
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Fuel Facility and Materials Safety
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Branch Dates of Inspection: December 7-9, 1976 RevLewed by:
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/3lMh4 g A. F. Gibson, Chief Date F
Radiation Support Section Fuel Facility and Materials Safety Branch 1.
Individuals Contacted J. Alberdi - Project Manager i
G. P. Beatty, Jr. - Nuclear Plant Superintendent i
G. R. Westafer - Technical Support Engineer J. R. Wright - Chemical and Radiation Protection Engineer J. L. Harrison - Assistant Chemical and Radiation Protection Engineer G. D. Perkins - Health Physics Supervisor
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W. A. Cross - Plant Engineer j
R. E. Fuller - Plant Engineer D. W. Padrick, IV - Compliance, Engineer
J. C.. Hobbs, Jr. - Manager, Generation Testir
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G. H. Ruszala - Test Engineer E. E. Froats - Managar, Site Surveillance 2.
Testing of Radioactive Wasta Sample Lines (75-19/4)
This item was originally discussed in IE Report no. 50-302/75-a.
19, Details III, paragraph 2 and dealt with the need to test t
waste sample lines to verify representative sampling and
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assess the amount of plate out in sample piping as required by
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The inspector discussed this item with
a licenses representative, who informed the inspector that i
testing was complete and the test results indicated no signifi-cant plate out or losses in the sample lines. The licensee representative also discussed the method of testing used and
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the problems which had been encountered during testing.
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b.
The ' inspector reviewed Addendum H to TP 7 1 360 2, Atmosphere Radiation Monitor Calibration and Functional-Test, which was used to perform the sample line test and verified that the test data j
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IE Rpt. No. 50-302/76-24 III-2
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i lines, that the addendum had been properly reviewed and approved i
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prior to the test and' that the test results had been reviewed and approved. The inspector had no further questions on this matter and advised licensee management that this item was considered closed.
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3.
Evaluation of Sampling Media Collection Efficiencies (75-19/6)
This item was originally discussed in IE Report No. 50-302/75-19 Details III, paragraph 4 and dealt with the need to establish the collection efficiencies for sample collection media, especially charcoal cartridges.. In IE Report No. 50-302/76-22, Details II,
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paragraph 3 it was noted that a modification would be accomplished on the four samplers at environmental release points to increase
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the residence time of the flow through the media and thus increase
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the sampling efficiency. The inspector observed two of the four samplers to be modified and noted that the modification had not been made to those samplers. A licensee representative informed the inspector that the modification would be completed, but until *
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such time as it was complete, an efficiency based on the lower residence time was being used. The inspector informed licensee management that this item remains open pending completion of the modification to the air samplers and establishment of the sampling efficiency in the appropriate procedures.
4.
Status of Previously Identified Deviations
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a.
Variation of Filter Systems for FSAR Statements (1) This item was orighally discussed in IE Rsport No. 50-302/ 76-3, Details II, paragraph 4, and dealt with devia-
tions from FSAR Table 9-15 for filter housings.
In IE Report No. 50-302/76-17, Details I, paragraph 4, it was noted that three of the four items of apparent deviation
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were resolved but that the differential pressure indica-
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tion for control complex filters had not been resolved.
(2) A licensee representative informed the inspector that the installation of the instrumentation to provide the differ-l ential pressure read-out in.the control room had not been started. This item remains open pending completion of the insem1lation and alignmaat of the instrumentation.
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b.
Chemical Fume Hoods Performance
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This item was originally discussed in IE Report No. 50-302/76-1, DetailsII, paragraph 3anddealtwithyhefacevelocities
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IE Rpt. No. 50-302/76-24 III-3 i
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of various chemical fume hoods being less than the recommended
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values of generally accepted industry practices. During the inspection licensee representatives provided the inspector
with copies of the final test results of the face veloticles I
which were performed on December 8 and showed average velocities
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greater than 125 fpm. The inspector also discussed the actions
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taken to correct these conditions with various liccusee repre-sentatives. The actions taken to correct this situation are j
discussed in the licensee's letter of December 13, 1976.
Based on the actions taken and the satisfactory test results, the inspector informed licensee management that this item was closed.
5.
Preoperational Test Procedures a.
The inspector reviewed the folloting completed test procedures
to verify completion of the te es, proper approval of changes
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or revisions, completion of corrective actions on exceptions
or deviations, review and approval in accordance with FSAR Section 13.2.6.9, and satisfactory test results:
TP 7 1 261 5 - Liquid Waste Functional Test
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1 1 360 2 - Atmosphere Radiation Monitor Calibration (
and Functional Test
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7 1 362 2 - Liquid Radiation Monitor IPOC and Functional Test
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..7 l' 363 2 Gamma-Instrument Pre op Ca11bration and ' ~-
Functional Test After reviewing the completed test procedures and the results, the inspector had no questions on these procedures.
b.
Test Guide TG-000-55-1, HEPA and Charcoal Filter In-place Leak Test, specifies the requirements for in-place testing of filters and charcoal absorbers in the containment purge, auxiliary building exhaust and control complex recirculatica ventilation systems. Testing has been completed on the filters but the results have not been approved. A licensee representa-tive informed the inspeer - *:iat the test guides were being
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held pending the receipt of additional test data from the contractor who performed the tests. These data relate to the i
flow distribution across the filter bank as required by the Technical Specifications. A licensee representative informed
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the inspector that a second contractor was.on site and would perform this test to provide the test data in the event that the data are not available from.the original contractor.
Completion of filter testing is incomplete..
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IE Rpt. No. 50-302/76-24 III-4
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6.
Geneous Waste System Modification l
a.
This item was origina Hy discussed in IE Report No. 50-302/76-14, Details I, paragraph 4, and dealt with a modification
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.j which was to be made to the gaseous waste system to instan a
pressure reducing valve upstream of monitor RM-All. The reducing valve is necessary to prevent overpressurization of the monitor when discharging from a waste gas decay tank.
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b.
The inspector observed that a reducing valve had been installed in the system but a waiver tag had been attached. A licensee representative informed the inspector the installed valve is a
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temporary valve and that the permanent valve vill be instaned l
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when it is received. The licensee representative also informed the inspector that a preliminary leak test had been performed on the discharge piping after the reducing valve was installed, but the final ratest had ' ot yet been performed.
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While reviewing the installation of the pressure reducing
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valve the inspector noted that the flow meter for the discharge
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control valve was downstream of the reducing valve. This results in a variable discharge rate due to the decreasing
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upstream pressure and an unknown discharge rate once the upstream pressure starts to drop. A licensee representative informed the inspector that this condition had been identified in a Field Problem and the engineering change notice had been changed to relocate the pressure reducing valve upstream,,of the flow meter. This work has not been accomplished.
i 7.
Status of Previously Identified Items
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The following facilities, systems and functional areas were reviewed
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by the inspector. These items were previously discussed in IE
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Reports as incomplete.
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a.
Discharges from laundry sump - A revision to OP-407, Liquid
' Waste Disposal System, has been issued to implement administra-
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l tive controls to permit discharges from the sump.
i b.
Wasta solidification - Procedures for the solidification of
'
i waste with no free liquid have not been prepared.
)
i c.
Decontaminscion room - The deccatamination room has not been j
j completed nor have temporary decontamination facilities been
{
j-provided.-
.
j d.
Make-up system letdown line - The shielding for the' letdown
line and the block orifice has not been installed.
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