IR 05000302/1976016
| ML19308D399 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 09/28/1976 |
| From: | Jape F, Robert Lewis, Rogers R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19308D397 | List: |
| References | |
| 50-302-76-16, NUDOCS 8002280710 | |
| Download: ML19308D399 (7) | |
Text
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IE Inspection Report No. 50-302/76-16 Licensee: Florida Power Corporation 3201 34th Street, South P. O. Box 14042 St. Petersburg, Florida 33733 Facility Name: Crystal River 3 Docket No.: 50-302
License No.: CPPR-51 Category: B1 Location: Crystal River, Florida Type of License: BWR, PWR, 2452,.ht Type of Inspection: Routine, Unannounced Dates of Inspection: August 31 - Septerher 3,1976 , Dates'of Previous Inspection: August 19-20, 1976 Principal Inspector: F. Jape, Reactor Inspector
Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch Accompanying Inspecto : R. F. Rogers, Reactor Inspector Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch A 7,b ' Principal Inspector: / # t. e < + _. " . F. Jape 7' Reactor Inspecgor 7 ' Date Reactor Projects Section No. 2 .! Reactor Operations and Nuclear Support Branch b Reviewed by: [. d e sM ' Date R.'C. Lewis, Chief ' Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch J
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. ' V .' ' . . IE Rp t. No. 50-302/76-16-2- - - . SUMMARY OF FINDINGS i I.
Enforcement Matters None , II.
Licensee Action on Previously Identified Enforcement Matters Failure to Maintain Instrument Calibration Labels Uo-to-Date (IE Report 50-302/76-11) Licensee's letter, dated August 9,1976, was reviawed and discussed with licensee management.
All commit =ents have not been completed.
. Item remains cpen.
(Details I, paragraph 2) III. New Unresolved Items 76-16/1 Annunciator Alarm Procedures AP-102 The licensee's approved alarm proceduras contained
different setpoints, sycptoms, and required actions for identical alarms in engineered safeguards trains A and B.
(Details II, paragraph 3) IV.
Status of Previously Identified Unresolved Items 75-8/3 Operability of Category I Hydraulic Shock and Sway ^ Suppressors (IE3 75-05)
The required surveillance procedure for periodic inspec-tion of snubbers and restraints has been issued.
Item is closed.
(Details I, paragraph 3) V, Unusual occurences None VI.
Other Significant Findings None VII. Management Interview A management interview was held on September 3,1976, with J. Alberdi, Project Manager, and other F?C personnel.
The. inspection findings were discussed. Concern was expressed regarding the finding related to review of approved alarm pro-cedures. A licensee representative stated that the procedures in question would be revised.
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. IE Rpt. No. 50-302/76-16 I-l '-? .a' / . , .. '... " ' DETAILS I Prepared by: ' /.'. 0 - - ' -~ i.
F. Jape, Reactor Inspector Date Reacter Projects Section No. 2 Reactor Operations and Nuclear . Support Branch Dates of Inspection: August 31-September 3,1976 Reviewed by: /3. 5.
,L M Y.Mf70 ' R. C. Lewis, Chief Date Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch 1.
Individuals Contacted Florida Power Corporation (FPC) n J. Alberdi - Project Manager G. P. Beatty, Jr. - Nuclear Plant Superintendent T. C. Lutkehaus - Maintenance Engineer S. Parker - Auditor K. O. Vogel - Computer and Controls Engineer 2.
Instrumentation Cali' ration Followup on the item of noncompliar.ceE! related to out-of-date calibration labels on safety-related instrumentation revealed that the commitments contc.:ned in the licensee's letter, dated August 9,1976, heve not been co=pleted. The status of corrective , ! action is as follows: a.
Revision of OP 14.11 "" e of Status Indicators" l A draf t has been prepared to delete the reference to permanently installed instrumentation and controls. Approval of this re- ' vision is expected within one month.
i b.
Interoffice Memo Addressing Calibration Labels ' No actio,n.
Conniement is to supercede the meno requiring calibration status lables.
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] ] ' m . s i , )) - . . . . IE Rpt. No. 50-302/76-16 I-2 , . Removal of Calibration Labels from Safety-Related Instrumentation -- c.
No action. Licensee management have stated that this commitment may be revised in a supplemental letter.
Followup on this deficiency will be continued on subsequent inspections.
3.
Operability of Category I Hydraulic Shock and Sway Sunpressors (IEB 75-05) The licensee's response to IEB 75-05 was reviewed during inspection ' 50-302/75-8. During that inspection unresolved item 75/8-3 was identified since the required surveillance procedures for periodic inspection had not been issued.
Followup on this item was conducted and unresolved item 75/8-3 is closed. Surveillance procedure SP-201, " Hydraulic Snubbers In- , spection," was issued August 6,1976, by the Nuclear Plant Super-intendent. The inspector found that this procedure incorporated all of the requirements contained in the proposed Technical Specification 3/4.7.9, " Hydraulic Snubbers."
' 4.
Maintenance Procedures I A representative sample of maintenance procedures was exa=ined using Section 1.7.6.7.1 of the FSAR and ANSI 18.7-1972, "Administra-i tive Controls for Nuclear Power Plants," as guidance. The procedures were found to be in conformance with licensee commitments.
The licensee's plans and policies for conducting and controlling maintenance activities are delineated in Al-600, " Conduct of Maintenance," and Al-900, " Conduct of Technical Support."
The inspector had no questions or comments following review of these documents. In general, the licensee's plans and policies are in agreement with FSt.R commitments.
The maintenance procedures listed below comprised the sample ex- ! amined: i MP-121, " Pump Repacking"
MP-124, " Disassembly and Reassembly of Emergency Ludwater Pumps" ! '~' s__ - , ... _ . -- ~ -
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. c r . I j-fE Rpt. No. 50-302/76-16 I-3 i l- ! I l MP-128, " Removal and Replacement of RC Pump' Hydraulic Shock l l Suppressors" i i MP-130, " Pipe Snubber Maintenance" . !' MP-201, " Nuclear Detector Removal and Replacement.
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. . - <x ( ) . N_/ IE Rpt. No. 50-302/76-16 II-1 _ DETAILS II Prepared by: 6/ L /2./
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F'. Rogers, Reactor Inspector // Date
Reactor Projects Section No. 2-Reactor Operations and Nuclear Support Branch.
Dates of Inspection: ,, Reviewed by: R. C. Lewis, Chief Date Reactor Projecer Section No. 2 Reactor Operations and Nuclear Support Branch 1.
Personnel Contacted J. Alberdi - Project Manager G. P. Beatty - Plant Superintendent P. F. McKee - Assistant Plant Superintendent e J. C. Hobbs, Jr. - Manager Generation Testing / D. W. Pedrick, IV - Compliance Engineer \\s R. S. Dorrie - Quality Engineer ,, ' 2.
Preooerational Test Results Completed Category I preoperational tests were reviewed to assure that the licensee had performed an adequate teview of test results, the test results were within established acceptance criteria, a method of identifying and correcting test deficiencies was being j followed, and administrative control practices were being followed in test results documentation. The following preoperational tests were reviewed: IP 71-451-15, 480 Volt Engineered Safeguards Switchgear TP 71-451-22, DC Power System Functional Test
TP-71-451-23, Station Battery High Voltage Equalization Charge TP-71-200-4, Reactor Coolant System Hydrostatic Test ' TP-71-204-4, RB Spray System Instrumentation Preoperational Calib ration i The inspector had no further questions.
3.
Review of Annunciator Alarm Procedure AP 102 This procedure was reciewed for conformance to the requirements . of ANSI N18.7-1972, " Administrative Controls for Nuclear Plants," ' Section 5.3.8, "E=ergency Procedures" and FSAR Section 12.4, < ... .. -..... _.
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) . - - x-s/ ' IE Rpt. No. 50-302/76-16 II-2 , . , . " Plant Procedures." AP 102 is a collection of~ individual alarm proceduros which detail actions required upon receipt of an - annunciator alarm light and buzzer.. The individual procedures were reviewed to ascertain whether they adequately controlled safety-related functions in.the event of system or component. , malfunction indication. A review of emergency safeguards panels A and B procedures revealed that the procedure for an alarm on the B panel was different than that for the same alarm on the A panel. Differences were noted in setpoints.
probable causes, symptoms, automatic cetion, and/or required . I operator action in 19 of the first 20 procedures compared.
AP 102 was reviewed by the plant revicw consittee (PRC) or.
i February 21,1976, 'and approved by the plant superintendent on February 25, 1976. It did not appear that the proceduru was adequately reviewed by the plant staff prior to issuance in that the procedural steps listed were substantially dif-i ferent for identical plant alarm conditions. A licensee representative stated that AF 102 would be reviewed and properly revised.
The adequacy of AP 102 is unresolved and is designated Unresolved ) Item 76-16/1.
_, 4.
Food and Water Supplies for the Control Room The inspector confirmed that the food and water supplies defined in FSAR Appendix 12B, Section 2.4.1, " Nuclear Plant Control Center" were available in the control roca. This outstanding item was initially discussed in Report 76-7 and is consid< 2d' closed.
5.
Operator Recualification i The inspector noted that the licensee had initiated its operator requalification program to assure a continuing high level of proficiency amoung licensed operators while awaiting plant operation.
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