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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20112G3871996-06-0404 June 1996 Potential Part 21 Rept Re Capscrews W/Trace Code of K7 Mfg by Cardinal Industries (Now Known as Accutech) & Distributed by Energy & Process Corp for Plant CP S/N 0194012.Pump/motor Would Remain Operational Throughout Worse Case Scenario ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20086G2931991-11-21021 November 1991 Part 21 Rept Re Failure of Model 763 & 763A Static Pressure Transmitters.Caused by Short Circuit in Connector Pin to Adjacent Mounting Screw.Engineering Drawings & Mfg Work Instructions Changed & Stock Purged of Subj Transmitters ML20059N5191990-10-16016 October 1990 Part 21 Rept Re Rod & Bearing Assembly Failures Noted by Wolf Creek Nuclear Operating Corp During Testing.Rept Will Be Issued Outlining Root Cause & Corrective Actions to Prevent Recurrence ML17223A7451990-01-26026 January 1990 Part 21 Rept Re Backup Rings Furnished in Spare Parts Seal Kits & in 25 Gpm 4 Way Valves as Part of Actuators Made of Incorrect Matl.Rings Should Be Viton & Have Been Identified as Buna N ML20246J0631989-08-29029 August 1989 Part 21 Rept Re Namco Refusal to Certify Design & Matls for Replacement Namco Limit Switches Supplied by Masoneilan. Initially Reported on 890825.Switches Put on QC Hold Until Final Disposition of Switches Determined ML20244D2901989-06-0101 June 1989 Part 21 Rept Re Buchanan 724 Terminal Blocks Supplied by Limitorque Corp,Rather than Correct Buchanan 524 Terminal Blocks.Caused by Error in Order Processing.Training Held to Ensure That Procedures Followed Correctly ML20235Y4811989-03-0303 March 1989 Part 21 Rept Re Cracked Welds Discovered on Striker Plates of GE Circuit Breakers.Initially Reported on 890130.GE Advised Util That Striker Plates Subj to Impact Loading Only When Breaker in Racked Out & Operated in Test Position ML20195F6191988-11-18018 November 1988 Part 21 Rept Re GE Magne-Blast Circuit Breakers.Initially Reported on 881116.Welds on All safety-related Breakers Will Be Repaired Prior to Entry Into Hot Shutdown ML20151W7841988-08-16016 August 1988 Part 21 Rept Re Cracking of Slides Used in Four Way Valves Furnished on Actuators for MSIVs Due to Brazing/Heat Treating of Slide Matl.All Sites Using Actuators Will Be Formally Notified by 880826.List Encl ML20151B4291988-04-0101 April 1988 Part 21 Rept Re Inconsistencies in Gould,Inc Certificate of Compliance Received W/Class 1E Fuses Procured from Planned Maint Sys Due to Fuses Not Being Qualified for Certain Specs.Initially Reported on 880329.Fuses Remain on Hold ML20234C7351987-06-23023 June 1987 Supplemental Part 21 Rept Re Silicone Foam Seal Anomolies at Wolf Creek Generating Station ML20211P7211987-02-23023 February 1987 Part 21 Rept Re Rockbestos Coaxial Cable Used in Sorrento Electronics Digital & Analog high-range Radiation Monitor. Insulation Resistance at High Temp Not High Enough for Ion Chamber & Associated Electronics to Operate Properly ML20153D8861986-02-17017 February 1986 Part 21 Rept Re Failure of Penetration & Conduit Seal Configurations During Fire Tests.Initially Reported on 860214.Evaluation of Number & Location of Defective Seals in Progress.Nrc Assistance Requested ML20137W2611985-09-30030 September 1985 Update to Part 21 Rept Re Insp for Cracked Welds Discovered in Generator Brackets.Insp for Callaway Unit 1 Postponed Until Next Refueling Outage (Probably Apr 1986).No Cracks Discovered During Insp at Wolf Creek ML20135E1161985-09-0505 September 1985 Part 21 Rept Re Use of Connectron non-IEEE Qualified Matl in Spare Part Terminal Blocks Supplied to Facilities. Appropriate Customers Notified.Terminal Blocks Should Be Reviewed to Identify Defective Matl ML20210G9921985-08-13013 August 1985 Part 21 Rept Re Failure of Isolated Worm Shaft Gear When Certain Critical Speeds Combined W/Repetitive Transfer of Actuator Clutch Mechanism from Manual (Handwheel) to Motor Drive Mode.Two Possible Solutions Noted ML20117B8141985-05-0101 May 1985 Part 21 Rept Re Ruskin Fire Dampers Installed at Facility. Initially Reported on 850426.Fire Dampers Found in Discrepant Condition Will Be Reworked in Order to Assure Integrity & Proper Functioning ML20116E8481985-04-23023 April 1985 Part 21 Rept Forwarding Rev 1 to Insp Procedure for Investigating Emergency Diesel Generators for Fractured Welds on Air Deflectors.Rev Will Be Forwarded to Each Facility ML20116D3201985-04-22022 April 1985 Part 21 Rept Re Ruskin Mfg Co Welds Used to Join Damper to Damper & Damper Section to Mullion Plates.Welds Not in Accordance W/Approved Design Drawings.Drawing 5415 Revised to Indicate Weld Spacing.Drawing of Weld Spacing Encl ML20115J1361985-04-15015 April 1985 Forwards Insp Procedure for Investigating Emergency Diesel Generators for Fractured or Cracked Welds to Determine If Part 21 Problem Exists,Per Jg Borman ML20100E0651985-03-29029 March 1985 Part 21 Rept Re Series of Cracked Welds Discovered in Generators.Welds Occurred in Conical Baffle Section of Coil Guards.All Units Will Be Inspected.Affected Plants Listed NRC-85-3024, Part 21 Rept Re Possible Undetectable Failures in ESF Actuation Sys.Initially Reported on 791107.Possibility of Undetectable Failures Remain Under Certain Circumstances Despite Change in Hardware1985-03-22022 March 1985 Part 21 Rept Re Possible Undetectable Failures in ESF Actuation Sys.Initially Reported on 791107.Possibility of Undetectable Failures Remain Under Certain Circumstances Despite Change in Hardware ML20102B9531985-02-13013 February 1985 Supplemental Final Deficiency Rept (53564-K159) Re Concrete Coatings Inside Containment.Initially Reported on 841213. Coated Concrete Surfaces Inside Containment Will Perform Satisfactorily Under DBA Conditions ML20107B6931985-02-0707 February 1985 Final Deficiency Rept (53564-K161) Re Uncertainties in Resistance Temp Detectors Calibr.Westinghouse Evaluation Demonstrated That Revised Resistance Temp Detectors Uncertainty Acceptable ML20101T1211985-01-25025 January 1985 Final Deficiency Rept (53564-K159) Re Concrete Coatings Inside Containment.Initially Reported on 841213.Destructive Adhesion Tests Performed on Locations Selected by Sampling Plan to Verify Acceptability of Coatings ML20104B1471985-01-18018 January 1985 Final Deficiency Rept Re Insp of Structural Steel Welds. Initially Reported on 840918.Structural Concerns Identified & Corrective Action Repts Issued to Have Shims Less than 1/4 Inch Thick Placed Flush W/Mounting Frame ML20104A8671985-01-13013 January 1985 Final Deficiency Rept Re Standby Diesel Generator B Left Bank Turbocharger.Initially Reported on 840504.Caused by Loose Lock Nut on Left Bank Turbocharger Lubricating Oil Pump Centrifuge.Damaged Turbocharger Repaired & Inspected ML20104A8171985-01-13013 January 1985 Final Deficiency Rept Re Subcooling Core Monitor Alarm & Caution Relays.Initially Reported on 840821.Interposing Relays & Diodes Added to Sys to Minimize Potential for & Suppress Effects of Any Arcs Generated ML20114C9141985-01-13013 January 1985 Final Deficiency Rept (53546-K158) Re ASME Hangers & Component Supports.Initially Reported on 841212.Insulation Contractors Revised Procedures & Retrained Personnel to Preclude Further Tampering of Supports ML20104B9241985-01-13013 January 1985 Final Deficiency Rept Re Water Damaged Limitorque Motor Operators.Initially Reported on 840203.Caused by Leakage During Sys Flushing & Hydrostatic Testing Activities.Seals Added Inside Conduit & T-drains Installed in Operator ML20114D1081985-01-13013 January 1985 Final Deficiency Rept (53564-K118) Re safety-related Field Procurement by Constructor.Initially Reported on 840103. Complete Review of Constructor safety-related Purchase Orders Completed.All Nonconformance Repts Resolved ML20114C8441985-01-13013 January 1985 Final Deficiency Rept Re Microbiologically Induced Corrosion in Hxs.Initially Reported on 840601.All HXs Utilizing Lake Water for Cooling Medium Eddy Current Inspected for Microbiologically Induced Corrosion ML20114C7981985-01-13013 January 1985 Final Deficiency Rept Re Removal & Replacement of ASME Components in Support of Cleaning & Flushing Activities. Initially Reported on 840711.Investigation Into Handling & Storage of ASME Components Removed from Sys Conducted ML20112D8061985-01-0404 January 1985 Final Deficiency Rept Re MSIV Lockwashers.Initially Reported on 841207.Lockwashers Installed Via Startup Field Rept I-SU-122 & Will Be Completed Prior to Fuel Load ML20112F5421985-01-0303 January 1985 Forwards Dec 1984 Status Rept Re 10CFR50.55(e)/Part 21 Open Items RBG-19-803, Final Deficiency Rept DR-234 Re Short Cap Screws,Shallow Bolt Holes,Damaged Dowel Pins & Damaged or Missing Lock Devices for Hanger Block Bolts in Check Valves Supplied by Velan Engineering,Ltd.Initially Reported on 8411281984-12-28028 December 1984 Final Deficiency Rept DR-234 Re Short Cap Screws,Shallow Bolt Holes,Damaged Dowel Pins & Damaged or Missing Lock Devices for Hanger Block Bolts in Check Valves Supplied by Velan Engineering,Ltd.Initially Reported on 841128 ML20101N0481984-12-0707 December 1984 Final Deficiency Rept Re RCS Resistance Temp Detector Calibr Data.Initially Reported on 840801.Manufacturer Calibr Procedures Revised to Allow Recalibr at Facility.All Resistance Temp Detectors Will Be Replaced or Refurbished ML20101K8531984-12-0707 December 1984 Final Deficiency Rept Re Certification of Lead Auditor for Technical Metals,Inc.Initially Reported on 840524.Samples from Production Lots Remaining in Site Warehouse Chemically Analyzed & Found Acceptable ML20101L5631984-12-0707 December 1984 Supplemental Final Deficiency Rept Re Installation of 3-h Rated Hollow Metal Fire Door Frames.Initially Reported on 840525.Existing Caulking Replaced W/Approved Flame Retardant Adhesive Sealant ML20101N1871984-12-0707 December 1984 Final Deficiency Rept Re Heat Numbers W/More than One Pipe Schedule.Initially Reported on 831213.Two Piping Spool Pieces Replaced W/Correct Schedule of Pipe.Exam of All Installations of Subj Heats Revised to Prevent Recurrences ML20101L3591984-12-0707 December 1984 Final Deficiency Rept Re Lubricating Oil Piping Sys for Safety Injection Pumps & Centrifugal Charging Pumps. Initially Reported on 840717.Replacement of safety-related Equipment W/O QA Program Will Be Repeated Per QA Program ML20101M1031984-12-0707 December 1984 Final Deficiency Rept Re ITE-Gould Containment Cooling for Mechanical Interlocks.Initially Reported on 840316. Instruction Manual Revised to Change Installation Instructions of Size 5 Mechanical Interlock Assembly ML20101D3011984-12-0505 December 1984 Forwards Status Rept for Oct & Nov 1984 Re 10CFR50.55(e) & Part 21 Items ML20100R5131984-12-0101 December 1984 Final Deficiency Rept Re Standby Diesel Generator Lube Oil keep-warm Pumps Supplied by Crane-Deming.Pumps Will Be Designed for Reliability.Interim Pumps Reliable for Use Until ASME Rated Pumps Available ML20100C1161984-11-19019 November 1984 Deficiency Rept Re Pressurizer PORVs Preoperational Test Discrepancies.Special Operations Procedure Will Be Performed to Resolve Existing Test Discrepancies ML20099K7801984-11-16016 November 1984 Final Part 21 & Deficiency Rept Re Turbine Driven Auxiliary Feedwater Pump Governor Valve Stem Guide Bushings.Initially Reported 841017.Investigation Revealed That Defictive Parts Described by Terry Corp Installed at Facility ML20099K8291984-11-13013 November 1984 Final Part 21/deficiency Rept Re Pressurizer PORV Failing to Close During Preoperational Test.Initially Reported 841011. Resolution Will Be Provided by 841119 ML20099H1601984-11-0909 November 1984 Final Deficiency Rept Re ex-core Neutron Detector Field Cabling.Initially Reported on 841009.All Damaged Triaxial Cables & Connectors Repaired &/Or Replaced.All Insulation Panels Verified to Be Properly Reinstalled 1996-06-04
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G1521999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Wolf Creek Generating Station.With ML20211N0161999-09-0202 September 1999 Safety Evaluation Supporting GL 95-07 to License NPF-42 ML20212A0251999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Wolf Creek Generating Station.With ML20217P6451999-08-30030 August 1999 Requests Commission Approval to Publish Encl Pr,Rg & SRP & to Issue Encl Ltr to Parties of Wolf Creek Transfer Proceeding Re Disposition of Existing Antitrust License Conditions in Event OL Transfer Approved ML20210R5741999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Wolf Creek Generating Station ML20210J1561999-07-29029 July 1999 Rev 0 to Wolf Creek Generating Station,Unit 1 Pressure & Temp Limts Rept ML20210R5921999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Wolf Creek Generating Station ML20209H0821999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Wolf Creek Generating Station ML20195D5261999-06-0202 June 1999 Safety Evaluation Approving Proposed ISI Program Alternative for Limited Reactor Vessel Shell Weld Exams & Relief Request from Requirements of ASME Code,Section XI ML20210R5871999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Wolf Creek Generating Station ML20195K1021999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Wolf Creek Generating Station ML20195K1071999-04-30030 April 1999 Revised MOR for Apr 1999 for Wolf Creek Generating Station ML20206P8261999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Wcgs.With ML20196L3401999-04-30030 April 1999 Rev 1 to WCGS Cycle 11 Colr ML20210R5841999-04-30030 April 1999 Revised Monthly Operating Rept for Apr 1999 for Wolf Creek Generating Station ML20205Q0761999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Wolf Creek Generating Station.With ML20207K5991999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Wolf Creek Generating Station.With ML20207K9761998-12-31031 December 1998 Annual SER 14,for Period 980101-1231, for WCGS ML20199E6531998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Wolf Creek Generating Station.With ML20195C0011998-12-31031 December 1998 Ks City Power & Light Co 1998 Annual Rept & Financial Statements as of 981231 & 1997 for Ks Electric Power Cooperative,Inc ML20195B9901998-12-31031 December 1998 Western Resources Annual Rept for 1998 ML20198D7321998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Wolf Creek Generating Station.With ML20195H9801998-11-17017 November 1998 Safety Evaluation Supporting Proposed Changes to WCGS Radiological Emergency Response Plan ML20195E7591998-11-10010 November 1998 WCNOC Proposed PASS Function Reduction ML20195D1791998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Wolf Creek Generating Station.With ML20154L4591998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Wolf Creek Generating Station.With ML20153G2771998-09-30030 September 1998 Rev 1 to WCAP-15079, Wolf Creek Heatup & Cooldown Limit Curves for Normal Operation ML20153G2851998-09-30030 September 1998 Rev 1 to WCAP-15080, Evaluation of Pressurized Thermal Shock for Wolf Creek ML20153G2691998-09-30030 September 1998 Rev 1 to WCAP-15078, Analysis of Capsule V from Wolf Creek Nuclear Operating Corp Wolf Creek Reactor Vessel Radiation Surveillance Program ML20153G7301998-09-23023 September 1998 Special Rept 98-003:on 980814,station Entered TS 3.3.3.6, Action Statment a Due to Inoperability of RVLIS B Train. Cause Has Not Yet Been Identified.Work Order 98-202813-000 Has Been Generated ML20151W1491998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Wcgs.With ML20237B7381998-08-14014 August 1998 Special Rept 98-001:on 980615,oxygen Analyzer on Wgs Was Declared Inoperable.Wgs Oxygen Analyzer OARC-1119A Was Indicating 0 Ppm on 980814 & Fluctuated Between 200 & 900 Ppm on 980615.Completed Work Order & Declared Wgs Operable ML20237B0841998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Wolf Creek Generating Station ML20236P3441998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Wolf Creek Generating Station ML20236P3481998-05-31031 May 1998 Corrected Page of MOR for May 1998 for Wolf Creek Generating Station ML20249A0171998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Wolf Creek Generating Station ML20249B2451998-05-18018 May 1998 Nonproprietary Version of Revised Chapters 4 & 5 to Rev 4 of HI-971769, Licensing Rept for Reracking of Callaway & Wolf Creek Nuclear Plants for Ue & Wcnoc. Chapters 4 & 5 Reflect Editorial Revs ML20248C3681998-05-18018 May 1998 Non-proprietary Version of Rev 4 to HI-971769, Licensing Rept for Reracking of Callaway & Wolf Creek Nuclear Plants ML20247H0901998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Wolf Creek Generating Station ML20216J7791998-04-15015 April 1998 SER Approving Requests for Relief I1R-46 Through I1R-49 & I2R-21 Submitted by Licensee on 970523.Relief for Exam Category B-A,Item B1.12,RPV Shell Welds Deferred Until Licensee Satisfies Regulations for Augmented Rv Exam ML20216C2641998-04-0606 April 1998 SER Accepting Addl Info Re GL 92-08, Thermo- Lag 330-1 Fire Barriers, for Plant ML20216F6101998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Wolf Creek Generating Station ML20217H3491998-03-31031 March 1998 SER Accepting Operational Quality Assurance Program Description Change for Wolf Creek Generating Station ML20217H7241998-03-30030 March 1998 SER Accepting Proposed Change to Operational Quality Assurance Program for Plant ML20216G1971998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Wolf Creek Nuclear Operating Corp ML20202H0721998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Wolf Creek Generating Station ML20217G4311997-12-31031 December 1997 Western Resources 1997 Annual Rept & Financial Statements for Years Ended 971231 & 1996 for Ks Electric Power Cooperative,Inc ML20203H0151997-12-31031 December 1997 Annual Operating Rept 13 for Jan-Dec 1997 ML20217G3711997-12-31031 December 1997 Kansas City Power & Light Co 1997 Annual Rept ML20216D7771997-12-31031 December 1997 Annual SER 12 for Jan-Dec 1997, for Wolf Creek Generating Station 1999-09-30
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> KANSAS GAS AND ELECTRIC COMPANY y THE ELECTFhC COMPANY
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OLENN L MOESTER vaca remosast asuctaan March 1, 1983 Mr. W.C. oeidle, Chief Reactor Projects Branch 2 U.S. Nuclear Reculatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 KMLNRC 83-018 Re: Docket No. STN 50-482 Ref: 1) Letter KMLNRC 82-211, dated June % 1982, from GLKoester, KG&E, to WCSeidle, NRC
- 2) Letter NS-EPR-2586, dated Oril 21, 1982 from EPRahe, Westinghouse, to RC'mYoung, NRC Subj: Interim 10CFR50.55(e) Report - Post Accident Instrument Errors
Dear Mr. Seidle:
Reference 1) provided an interim report on a 10CFR50.55(e) matter concerning the potential, post-accident errors in the reactor coolant system wide range pressure instruments. Westinghouse reported this matter to the NRC on a generic basis in Reference 2) and the NRC disseminated the subject in IE Information Notice No. 82-11.
Westinghouse determined that the post-accident accuracy of the wide range pressure instruments may not meet functional requirements.
Kansas Gas and Electric Company has reviewed this matter with Westinghouse and has determined that, for most functions dependent on wide range instruments, the potential inaccuracies do not constitute a significant deficiency for the Wolf Creek Generating Station. A summary of the evaluation that leads to this conclusion is provided in the attached report. The effects of the potential inaccuracies on the reactor vessel level instrumentation system and core cooling monitor system are still being evaluated. The status of that evaluation will be reported to you on or before July 1, 1983.
In the interim, please direct any questions on this matter to me or to Mr. Otto Maynard of my staff.
8303080498 830301 Yours very truly, PDR ADOCK 05000482
'. g GLK: b Attach cc: RCDeYoung, w/a TVandel/SSchum, w/a 201 N. Market - WicNta, Kansas - Mail Address: PO. Box 208 I Wichita, Kansas 67201 - Telephone: Area Code (316) 261-6451
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THE EFFECT OF POTENTIAL i
i POST-ACCIDENT ERRORS IN U:E O
WIDE RANGE REACTOR COOLANT SYSTEM PRESSURE INSTRUMENTS
[ ON THE SNUPPS PLANTS I
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' I 5ttachment KMLNRC 83-018 Introduction In early April 1982, Westinghouse informed SNUPPS of a potential signifi-cant deficiency, as defined by'10CFR 50.55(e), for the SNUPPS plants concerning the potential, post-accident inaccuracy of the reactor
- coolant system ~(RCS) wide range pressure instrument. This Westinghouse determination was based on a review of the results of equipment qualifi-cation testing and of design / operational requirements.placed on the instrument. Westinghouse also recognized that due to the complexity of the' issue and plant-specific differences, the issue may affect individ-ual plants differently. Tne SNUPPS plants (Callaway and Wolf Creek) are identical insofar as this issue affecting, or being affected by, olant design and operation. Therefore the SNUPPS Utilities jointly reviewed this matter. The review include'd Westinghouse and the architect /
engineer for SNUPPS, Bechtel Power Corporation.
4 Normal Plant Operations and Evolutions In a normal plant environment, the RCS wide range pressure instrument has an indication accuracy of + 90 psi (3% of span) and a trip and actuatian accuracy of + 63 psi-(2.1% of span). During plant operation, the' instrumentation is'~used to monitor RCS pressure outside of the
, narrow range pressurizer pressure measurement. The indication accuracy l provided is acceptable for this function. '
i For initiation of Residual Heat Removal System (RHRS) operation, the
( instrumentation provides an open permissive signal to the RHRS isolation L valves. The system pressure requirements are based on precluding over '
pressurization of the RHRS and yet maintaining a sufficient RCS pressui-to maintain the required differential pressure on the #1 Reactor Coolant l
Pump seals. The actual allowance in the SNUPPS design is + 117 psi.
Therefore the j; 90 psi indication and j; 63 psi trip accuracies are acceptable.
l l The RCS wide range pressure transmitter provides an input signal to the l overpressure mitigation system (OMS). in the SNUPPS design. Analyses of the OMS have shown that the + 63 psi trip accuracy is acceptable.
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Attachment
. KMLNRC 83-018 Page Two Abnormal / Accident Conditions 4
In the worst case accident environment, the RCS wide range pressure instrument accuracies are + 390 psi (13% of span) for irdication and
+ 363 psi (12.1% of span) Tor trip and actuation. These values assume a
+ 10% sensor environmental allowance based on the environenntal testing described above and also reflect normal sensor and sign _. processing allowances for calibration accuracy, drift, comparator setting, tempera-ture'effect, indicator accuracy, and indicator readability. During accident conditions the RCS wide range pressure signal is relied upon in '
several of the emergency response guidelines developed by the Westing-
, house Owners' Group and provides an input to the Reactor Vessel Level Instrumentation System (RVLIS) and the Core Cooling Monitor System
- (CCMS).
1 The emergency operating procedures for the SNUPPS plants have not been completed. However, they will be based on Westinghouse Owners' Group
- Emergency Response Guidelines (ERG). ERGS E-1 (Loss of Reactor Coolant) and E-2 (Loss of Seconoary Coolant) use RCS pressure for the operator evaluation of safety injection (SI) termination. The purpose of the
- evaluation is to minimize the number of demands on the pressurizer power-
}
operated relief valves and yet maintain subcooling following a small LOCA or steam system break.. Westinghouse has determi,ned that an accuracy of
- +325 psi'is required for this function and thuskis not met by the + 390 L accuracy of the RCS wide range pressure instrument. However, narrow rang.e t pressure instrumentation has a post-accident accuracy of about + 144 psi
,' - and its range (1700 to 2500 psig) includes the SI termination v'aTue (RCS
' pressure greater than 2000 psig). Use of the narrow range instrument for l this post-accident function has the advantage that the operator uses the same instrument that is used during normal plant operation and that is most familiar to h'im. If, during the finalization of the emergency operating procedures for the SNUPPS plants, (a) the accuracy require-ment for the SI termination function is not reduced, or (b) the accuracy of the wide range pressure instrument is not improved, the procedures will specify use of the narrow range instrument for SI termination; and equip-ment qualification documentation will show that the required accuracy is met. -
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Attachment' XMLNRC 83-018 Page Three ERG E-2 also uses wide range pressure for SI termination to minimize reactor vessel thermal shock while maintaining subcooling. The accuracy
~
requirement for this function is j; 520 psi and the post-accident accu-racies are acceptable.
ERG E-3 (Steam Generato'r Tube Rupture) uses the RCS wide range pressure instrument for a variety of functions. However the ERG requires only that a pressure increase be read. A specific accuracy is not required.
In addition, the tube rupture accident would not result in a harsh postaccident environment that could cause the large inaccuracies.
ERG E-0 (Reactor Trip or Safety Injection) requires that the operators evaluate the need to trip the reactor coolant pumps. This step ensures that pumps are kept running for accident conditions in which decay heat removal via the steam generators is preferred. For SNUPPS, the allowed instrumentation accuracy is about j; 530 osi. Therefore the wide range RCS pressure instrument meets this requirement.
The-CCMS compares core outlet thermocouple temperatures and hot and cold leg RTD temperatures based on the lowest of three pressure signals.
One of the three pressure signals for each of the redundant portions of the.CCMS is the RCS wide range pressure. The effect of the uncertainty of the wide range pressure signal is still under evaluation.
The RVLIS measures the differential pressure between the bottom and top
, of the reactor-vessel. To provide accuracy for level measurement, temperature of the impulse lines, RCS temperature, and RCS wide range pressure are used to compensate the differential pressure transmitter
. outputs for differences in system and reference leg density. The effect l .of the wide range' pressure instrument accuracy for RVLIS is also still under evaluation.
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r Attachment KMLNRC 83-o18 Page Four As described in the SNUPPS FSAR Appendix 5.4A, the SNUPPS plants are designed to attain a cold shutdown condition using only safety-grade equipment. Part of the safety-grade cold shutdobin scenario is the use of the RHRS. The post-accident- accuracies of the RCS wide range pressure transmitter are greater than + 117 psi. However, the SNUPPS design and licensing commitments do not 17equire that the RHRS be initiated in a normal mode following a design basis accident. For a postulated accident scenario in which the RHRS is eventually used in its normal cooling mode, other pressure instruments can be used to insure the safe initi-ation of the RHRS. Specific instruments.available for this purpose are the third RCS wide range channel, for which the pressure transmitter is located on one of the RVLIS lines outside containment, and RCS pressure ,
instruments in the nuclear sampling system. Therefore, post-accident accuracies of, the instrument in question do not apply to RHRS initiation.
Conclusions There are no concerns about RCS pressure measurement during normal
- plant environmental conditions. Several of the guidelines that will be used as a basis for the operating procedures call for operator use of RCS wide range pressure. In all cases, either the required accuracy meets the demonstra.ted accuracy or a more accurate instrument will be used.
The RCS wide range pressure instrumcnt provides an input to other instru-mentation systems that may be used in a post-accident situation. In these cases, the safety effects of the wide range pressure transmitter inaccuracies are currently under evaluation.
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