IR 05000271/1985034
| ML20137M963 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 11/26/1985 |
| From: | Jerrica Johnson, Kucharski S, Petrone C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20137M944 | List: |
| References | |
| 50-271-85-34, NUDOCS 8512040041 | |
| Download: ML20137M963 (11) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-271/85-34 Docket No.
50-271 License No. OPR-28 Licensee:
Vermont Yankee Nuclear Power Corporation RDS, Box 169, Ferry Road Brattleboro, Vermont 05301 Facility Name: Vermont Yankee Nuclear Power Station Inspection At: 'Vernon, Vermont Inspection Conducted: -October 28 - November 1, 1985 Inspectors:
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- Af[/r-C. Pe~tr'one, Le d Rea r Engineer
' date Idb n/.x/x
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S, Kucha'rski, Reactor Engineer
/ dat(e Approved by:
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J. Johnson, Chief, Operational Programs date-Section, OB, DRS Inspection Summary:
Inspection on October 28 - November 1, 1985 (Report No. 50-271/85-34)
Areas Inspected:
Routine unannounced inspection of the Surveillance Testing and Calibration Control Program, startup testing'of modified systems, and licensee actions on previous NRC findings.
The inspection involved 58 hours6.712963e-4 days <br />0.0161 hours <br />9.589947e-5 weeks <br />2.2069e-5 months <br />
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onsite b;r two region-based inspectors.
Results: No violations were identified.
8512040041 851129 PDR ADOCK 05000271 o
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DETAILS 1.
Persons Contacted Vermont Yankee
- F. Burger, QA Coordinator
- L. Doane, Shift Supervisor
- R. Lopriore, Maintenance Supervisor M. Metill, Engineering Support
- J. Pelletier, Plant Manager R. Wanczyk, Technical Services Superintendent T. Watson, I&C NRC
- W. Raymond, Senior Resident Inspector 2.
Licensee Action on Previous Inspection Items 2.1 (Closed) Unresolved Item 83-31-02 Surveillance Test Program A review of procedure AP 4000, " Surveillance Testing Control", during inspection 83-31 identified that the procedure did not contain in-structions to require that Technical Specification (T.S.) amendments be reviewed for possible changes to surveillance test procedures.
During this inspection, the latest revision (revision 8) of AP 4000 was. reviewed and found to contain specific instructions for the re-view of Technical Specification amendments.
The inspector also reviewed a sample of recent T.S. amendments and verified that the-appropriate surveillance test procedures had been revised to reflect these changes. This item-is now closed.
2.2 (Closed) Unresolved Item 84-07-01 Effluent Monitoring Instrumentation
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Review of effluent monitoring instrumentation during inspection 84-07 identified-that procedure 0P 4315, " Main Steam Line Radiation Monitoe Scram - Isolation Functional / Calibration" did not indicate the toler-ance limits that must be met when functional tests are performed and did not require that a re-calibration be performed when the monitors are found outside tolerance limits.
Subsequently the licensee revised procedure OP4315 to correct these deficiencies. The inspector reviewed revision 7 of the procedure, dated April 12, 1985, and confirmed that these changes had been
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completed satisfactorily.
Th',s item is now closed.
2.3 (Closed) Inspector Follow-up Item 83-17-05 Reactor Mode Switch On June 15, 1983, an inadvertent scram signal was generated when the
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operators attempted to chance the mode switch position from " Shut-
-down" to " Start-up". The scram signal occurred when the mode switch hung-up momentarily between the " Shutdown" and the " Refuel" positions due.to excessive play in the operating linkage which, at times, makes-it diff cult to make a smooth transfer between positions. This item was left open pending completion of the licensee's long-term plans to
. improve the mode switch operation.
During this inspection, the inspector reviewed the licensee's plans to correct this problem and confirmed that the mode switch would be replaced during the current pipe replacement outage. These plans were reviewed and found satisfactory to resolve the inspectors con-cern. This item is now closed.
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2.4 (Closed) Unresolved Item 45-99-H2 Vermont Yankee Containment Isolation valves - compliance with Appendix J On August 19,.1983 the licensee received NRR acceptance of their-latest proposal of the containment isolation valves for type C testing.
This item is now closed.
2.5_-(Closed) Unresolved Item 76-16-01 Containment Leak Rate Testing Conformance to Appendix J Review of the integrated leak rate test program during inspection 76-16 identified various areas of-the procedure and the technical-specifications which involved changes to the penetrations and con-tainment isolation valves which are subject to type 3 and C testing and also which are exempt from type B and C testing. Based on NRC's August 19, 1983 response to Vermont Yankee's proposal (NVY 83-192),
this item is now closed.
2.6.- (Closed) Unresolved Item 76-16-04 Containment Integrity The_ licensee's procedure now requires any containment isolation valve or substitute valve to meet the leak test requirements of the type C test. This item is now closed.
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2. 7.
(Closed} Unresolved Item 76-16-05 Drywell to Torus Bypass Flow Area Test Adequacy-The' inspector reviewed procedure OP4115, Vacuum Breaker Operability and Technical File Calculation (Drywell: Leak Detection). Based on this review the constant temperature assumption is a conservative method of calculating a bypass leakage. This item is now closed.
2.8 (Closed) Unresolved Item 78-06-01 Administrative Control over RCIC, LPCI and HPCI - Torus suction drain line valves The inspector reviewed the P&ID and also reviewed OP-4030 (Contain-ment Leakage Rate Test) for valve alignment. The torus suction drain
.line valves are closed and capped. This item is now closed.
2.9 (Closed) Unresolved Item 78-06-02 TIP purge line isolation provisions and CILRT Alignment The inspector reviewed OP4030 (Containment Leakage Rate Test Type C Leak Rate Test) for the adequacy of isolation and testing for the TIP purge line valves. The licensee now has adequate provisions for testing and isolation. This item is now closed.
2.10 (Closed) Inspector Follow-up Item 83-01-01 Reactor Vessel Level Calibration Error An error was discovered in the calibration data used for calibration of the Rosemount level instrumenta ion. General Electric Co. was supplying the calibration data fo: the Yarway instruments assuming no heat clamps were installed. When installation was made heat clamps were used. -The instrument setpoints were set sufficiently high such that, even.with the error, all the trips occur within the technical specification required values. During the 1983 outage, the heat clamps were removed from the Yarway columns and the Rosemount level instruments were recalibrated. Thisaitem is now closed.
2.11 (Closed) Inspector Follow-up Item 83-18-01 MSIV Leakage to be added to Type B and C Sum The inspector reviewed FVY 83-97, Primary Containment Leak Rate Test-Report, and determined that'the licensee now accounts for MSIV leak-age in the total for Type C leakage.
This item is closed.
2.12 (Closed) Inspector Follow-up Item 83-18-03 Corrections to Preliminary ILRT results to be reported in Summary Technical Report Review of FVY 83-97, Primary Containment Leak Rate Test Report, shows that the licensee now accounts for the increase in drywell sump lev-els, increase in reactor vessel water level and leakage of isolation valves that were not accounted for during the test. This item is now close,
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3.0 Surveillance Testing Program The inspector reviewed the program for surveillance tests, calibrations,
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Specifications..The program and administrative procedures were examined to verify that:
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Responsibilities have been assigned for performance of tests and test schedule; Implementing procedures for performance of tests have been
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established; A master schedule for surveillance and calibration tests has been
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established; and, that
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Methods and responsibilities have been established for review and evaluation of data, for reporting of deficiencies and failures identified during surveillance test and calibration.
The' licensee's procedure A.P. 4000, " Surveillance Testing Control", dat'ed
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September 6,1984, provides instructions to plant personnel for implement-ing the surveillance testing programs required by Technical Specifica-tions 6.5.A.6.
Most surveillance activities with a recurring frequency of once per week or less are contained in a surveillance test schedule which is maintained, published, and independently verified by the
' Engineering Support Supervisor or Surveillance Test Coordinator (STC).
It requires that changes to the schedule caused by published changes to plant procedures be-submitted to the STC in writing by the department supervisor. The STC also maintains a conf. rolled copy of Plant Technical Specifications and incorporates TS amendments into the Surveillance Test Schedule.
The scheduling of tests with a frequency greater than once per week is assigned to the responsible Department Head. Actual development and implementation of test procedures and collection, review, and reten-tion of data are the responsibility of the department performing these
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3.1 Surveillance Test Review The inspector reviewed a sample of completed weekly surveillance test status sheets which included all tests performed during the month of September, 1985. The status sheets dated September 1, 9, 17 and 24 indicated that all required surveillance tests had been completed as scheduled, or rescheduled and completed within the required surveillance interval.
The inspector chose a sample of these tests for review of the completed test procedures. The test procedures were reviewed to verify the following:
they had been completed on the date specified on the status sheets; all required
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data had been recorded; results met acceptance criteria; all required pre-requisite and verification signatures were complete; and, QC
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review had been performed where required.
The following tests were reviewed:
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Technical Date.
Test Specification Complete Test Description Procedure Requirement,
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9/9/85 1-High Steam Line Radiation Funct. Test 4315 4.1.1 9/13/85 2-APRM High Flux Funct. Test 4302 4.1.1
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9/13/85
' 3-Drywell/ Torus Diff. Pressure Funct.
4379 4,7.A.9.8, Test 9/13/85 5-APRM Inop Funct. Test 4302 4.1.1 9/13/85 7-APRM Downscale Funct. Test 4302 4.1.1 r >
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9/10/85 9-Backfill Torus Level Reference Chamber 5374 N/A 9/12/85 122-LPCI Low-Low Reactor Vessel Water 4337 4.2.1
Level Funct. Test 9/12/85 123-LPCI Reactor Vessel Shroud Level 4337 4.2.1 Funct. Test 9/12/85 129-LPCI Low-Low Reactor Vessel Water 4337 4.2.1
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Level Funct. Test 9/12/85 134-ADS-Low-Low Reactor Vessel Water Level 4337 4.2.1 Funct. Test
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9/9/85 136-ADS-Bus Power Monitors Funct. Tert 4345'
4.2.1 9/12/85 137-Primary Containment Isolation-Low-Low 4313 4.2.2 Reactor Vessel Water Level Funct. Test 9/10/85 138-Primary Containment Isolation-Steam Line 4322
"4.2.2 Area High Temperature Funct. Test
9/11/85 140-Primary Containment Isolation-Steam Line 4324 4.2.2 Low Pressure Funct. Test t
v 9/12/85 141-Primary Containment Isolation-Low 4313
'N 4.2.2 Reactor Vessel Water Level Funct. Test 9/12/85 144-Low Reactor Water Level Instrumentation 4313 4. l.' 1 Funct. Test
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9/13/85 146-Turbine Control Valve Fast Closure 4314 4.111 Funct. Test
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9/12/85 151-Core Spray Actuation-Low-Low Reactor 4337 4.2.1 Vessel Water Level Funct. Test 9/9/85 156-Primary Containment Isolation-Main Steam 4315
,a 4.2.2 Line High Radiation Funct. Test 9/12/85 158-HPCI Isolation-Reactor High Water Level 4337 4.2.2 Funct. Test
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9/9/85 164-RCIC Isolation-Main Steam Line Tunnel 4366
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4.2.2 Temperature Funct. Test 9/9/85 165-RCIC Isol-Steam Line Space Temperature 4366 4.2.2
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Funct. Test 9/10/85 166-RCIC Isolation-Steam Line High dp 4364 4.2.2
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Funct. Test
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9/12/85 167-RCIC Isolation-Reactor High Water 4337 4.2.2 Leve1 Funct. Test s
9/10/85 168-RCIC Isolation-Steam Supply Low Press.
4365 4.2.2 Funct. Test 9/9/85 169-RCIC Isolation-Bus Power Monitor Funct.
4367 4.2.2 c,
E Test-x 9/12/85 170-RBV & SGTS Isolation-Low Reactor Vessel 4313 4.2.3 Water Level Funct. Test-
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9/12/85 258-Reactor Water Level-Main Turbine Trip 4337 N/A
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Funct. Test 9/12/85.289-RPT Low Low Reactor Vessel Water Level 4337 4.2.1 Funct. Test 9/12/85 291-RPT. Trip System Logic Funct. Test 4342 4.2.1
~, 9/10/85 310-Primary Containment Isolation Main 4324 4.2.2 s
Steam Line Low Pressure Cal.
9/13/85- -327-Turbine Control Valve Fast Closure 4314 4.1.2
Instrumentation Cal.
'9/13/85 328-H and 0 M nitors Funct. Cal.
4344 Pending
2 9/10/85-415-Strong Motion Accelerograph Funct.
4396 N/A Test
,9/9/85 80-MSIV Partial Closure 4113 4.7.D.I.c
'9/12/85 80-MSIV Partial Closure 4113 4.7.D.1.c 9/9/85 15-H Leakage Check 4161 N/A 9/9/85 20-Alt. Condensate and Demin. Water 2185 N/A Transfer Pumps
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9/15/85
'41-Control Rod Exercise 4111 4.3.A.2
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-9/5/85 182-Reactor Vessel Water Level Perturba-4172 4.1.1 p /)
- iion Test (Upon Completion of I&C y
(urveillance)
9/9/85,. 186-SLCS Pumps Test 4114 4.4.A.1
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9/11/85 189-HPCI Pump and Motor Operated Valve 4120 4.5.E.1 Oper. Test 9/11/85 190-RCIC Pump and Motor Operated Valve 4121 4.5.G.1 Oper. Test 9/11/85
~294-Vacuum Breaker Operability 4115 4.7.A.6.a 9/10/85 197-Standby Gas Treatment Heater 4117 4.7.B.2.d
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Operability Test y
w 3.2 Test Results During this review the inspector identified that the shift super-viso'r(s signature was missing from data sheets VYOPF 4114.01, dated Septemby 19, 1985 for pumps A and B.
This signature is required by OP,4114,'" Standby Liquid Control System Surveillance Procedure
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Rev. 14, Step 1.
The licensee corrected the signoff sheets.
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inspector noted that the shift supervisor had signed the other sig-nature block at'the bottom of the data sheet verifying that the test-had been completed satisfactorily.
- During review of a HPCI Monthly Valve Test Data Sheet VYP0F 4120.02,
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performed oVSeptember 11, 1985, the inspector noted that the ISI test coordinator's. review signature was missing from two of the three data sheet pages. The test coordinator subsequently re-reviewed and signed these data sheets.
As a result, the inspector chose a random sample of fifty additional data sheets,.from various surveillance tests, and reviewed them to
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determine if any verification signatures were missing.
No additional
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Based on this review, the in-s spector concluded that these examples were isolated cases. The sur-veillance records were generally well maintained, complete, and adequately controlled.-
3.3 Technical Specification Amendments The inspector reviewed a sample of-TS amendments to determine if these changes had been incorporated in the surveillance program. The inspector verified that the licensee had administrative controls in place to ensure TS amendmepts are reviewed by appropriate personnel for possible changes to surveillance procedures and schedules. The six most recent TS amendments (84-89) were selected for review. The inspector verified that the appropriate procedures had been revised to reflect changes in required frequency, and set points. No dis-crepancies were identified.
3.4 Quality Control Review of Surveillances Activities The inspector reviewed the Quality Control inspection records and noted that QC had reviewed the results of surveillance procedures 0P-4313, OP-4337, OP-4363, and OP-4340, during the month of Septem-ber.
The inspector.co'ncluded that Quality Control is actively involved in the witnessing 1and review of surveillance testing.
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3.5 Reactor Mode Switch ReplaceInent The inspector reviewed the licensee's plans to replace the reactor mode switch during the present outage.
The inspector discussed the planned replacement with cognizant licensee personnel and reviewed a preliminary draft of the procedure " Installation / Test Procedure For Replacement of SB-1 Reactor Mode Switch". The licensee purchased a replacement SB-1 mode switch from GE, the original vendor. ~ Due to limited space under Control Room Panel (CRP) 9-5, the switch will be
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removed with the wiring harness attached.
The switch will be taken to tne I&C shop where the wiring configuration will be compared to
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applicable plant drawings.
The harness will be inspected and then transferred to the new switch. The configuration will be verified to ensure that it will match the configuration of the old switch, then reinstalled in CRP 9-5.
This procedure was reviewed to ensure it contained adequate pre-requisites, appropriate precautions, clear procedure steps, accept-ance criteria, system lineups and tagouts, QC holdpoints, and post
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The inspector noted several minor discrepan-cies in the draft procedure which the licensee agreed to correct.
-The inspector noted that the post-installation checkout included comprehensive continuity checks of the switch and wiring harness.
The inspector had no further concerns.
J4.0 Calibration Program 4.1 Documents Reviewed 0.P. 4301, Intermediate Range Monitor Functional / Calibration,
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Revision 5, February 2,1984.
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0.P. 4302, Average Power Range Monitor Functional, Revision 7,
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March 6,~1985.
0.P. 4311, Drywell High Pressure Scram / Isolation Functional /
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Calibration, Revision 10, August 3, 1984.
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~0.P. 4313, Reactor Water lo Level Scram - Isolation /Lo Lo Level Isolation Functional / Calibration, Revision 17, July 30,1984.
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0.P. 4315, Main Steam Line Radiation Monitor Scram-Isolation
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Functional / Calibration, Revision 7, April 12, 1985.
0.P. 4322, Main Steam Line Area High Temperature Functional /
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Calibration Test, Revision 6, August 4, 1984.
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0.P. 4323, Main Steam Line High Flow Functional / Calibration
_ Revision 13, June 27, 1985.
0.P.-4335, Reactor Building Vent and Standby Gas Treatment
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System Logic Power Monitor Functional Test, Revision 9, June 21, 1984.
0.P. 4337, Reactor Water Level ECCS Initiation-Isolation
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Functional / Calibration, Revision 16, August 24, 1984.
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F 0.P. 4338, Drywell High Pressure ECCS Functional / Calibration,
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Revision 11, August 2, 1984.
0.P. 4342, Reactor Pressure ATWS/RPT/ECCS
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Functional / Calibration, Revision 3, August 4, 1984.
0.P. 4345, Auto Depressurization System Power Monitor
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Functional Test, Revision 9, January 21, 1985.
0.P. 4347, Core Spray Header Differential Pressure Functional /
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Calibration, Revision 9, January 21, 1985.
0.P. 4352, RHR Pump Discharge Pressure Functional / Calibration,
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Revision 10,1 January 21, 1985.
0.P. 4359, HPCI System Power Monitor Functional Test,
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Revision 11, January 21, 1985.
0.P. 4363, Functional Test of the HPCI Suction Valves Auto
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Transfer due to Condensate Storage Tank (CST) Low Level and Calibration of CST Level Loops and Associated Instruments, Revision 13, July 16,1985.
IC02.1.1, Administrative Control of Technical Specification
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Insturment Setpoints, Revision 1, March 28,1985.
File No. 3.3, Master Surveillance Test, April 15, 1985.
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4.2 Scope of Review The inspector reviewed the above listed documents for technical adequacy and to ascertain compliance with regulatory requirements, technical specifications and applicable industry standards. The-inspector also held discussions with the licensee regarding the im-plementation of the procedures, documentation of the results, and the frequency in which they are performed.
discussed below.
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Further details are 4.3 Procedure Review The inspector noted in reviewing procedure IC02.1.1, Administrative Control of Technical Specification Instrument Setpoints, that each plant instrument which has technical specifications requirements is listed with the technical specification limit, the Vermont Yankee trip setting limit and the functional and calibration frequency.
Also given for each instrument is the operations procedure for that instrument which verifies the information given in the Administrative procedure. No unacceptable conditions were identified.
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4.5 Results Review The inspector reviewed the latest functional test and calibrations performed in the procedures listed in Section 4.1.
They were re-
-viewed to see if the acceptance criteria was met, the documentation was complete, and the latest approved revision of the test procedure was reviewed. No unacceptable conditions were identified.
4.6 QA/QC Involvement During review of the results for individual functional test and cal-ibrations, the inspector noted that seven of the 17 procedures re-viewed were witnessed and audited by QA. No unacceptable conditions
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5.0 Facility Tours The inspector made several tours of the facility during the course of the inspection including the reactor building, turbine building and control room. _The inspector observed work in progress, housekeeping and clean-
'liness. No unacceptable conditions were identified.
6.0 Exit Meeting An exit meeting was held on November 1,'1985 to discuss the inspection scope and findings as detailed in this report (see paragraph I for attendees). At no time during the inspection was written material given to the licensee.