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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20211N0161999-09-0202 September 1999 Safety Evaluation Supporting GL 95-07 to License NPF-42 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 ML20195H9801998-11-17017 November 1998 Safety Evaluation Supporting Proposed Changes to WCGS Radiological Emergency Response Plan 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 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 ML20202B9791997-11-26026 November 1997 Safety Evaluation Accepting Relief Requests 2VR-7 VR-8 from ASME Boiler & Pressure Vessel Code,Section XI Requirements for Inservice Testing Program ML20198Q2821997-10-24024 October 1997 Safety Evaluation Granting Relief for Second 10-yr Interval ISI Program Plan & Associated Requests for Plant ML20217J7071997-10-0909 October 1997 Safety Evaluation Accepting Second 10-yr ISI Interval Relief Request I2R-22 ML20141D0501997-06-23023 June 1997 Safety Evaluation Supporting Requests for Relief to Use ASME Code Case N-508-1 for Plant ML20147C1561997-01-31031 January 1997 Safety Evaluation Accepting Licensee Structural Integrity & Operability ML20247N1811989-09-20020 September 1989 Safety Evaluation Supporting Plant Inservice Testing Program & Request for Relief ML20236C7501989-03-0909 March 1989 SER Supporting Util 880801 Request for Relief from ASME Code Pump & Valve Inservice Testing Program Requirements for Bearing Temp for Safety Injection Pumps ML20153E6921988-09-0101 September 1988 Safety Evaluation Accepting Licensee Program for Equipment Classification & Vendor Interface ML20151H1411988-07-19019 July 1988 Safety Evaluation Accepting Util Response to Generic Ltr 83-28,Item 4.3 Re Reactor Trip Breaker Automatic Shunt Trip ML20151G5121988-07-15015 July 1988 Safety Evaluation Supporting Amend 17 to License NPF-42 ML20195K0801988-06-17017 June 1988 Safety Evaluation Supporting Amend 16 to License NPF-42 ML20155G1041988-06-0101 June 1988 Safety Evaluation Re Diesel Generator Circuit Breaker Manual Close Capability.Final Design Acceptable ML20153F8471988-05-0202 May 1988 Safety Evaluation Granting Util Relief from Section XI of ASME Code Re Replacement of Parts on Two Code Classed Components ML20147D9631988-02-25025 February 1988 Safety Evaluation Accepting Util 860404 Evaluation of Environ Qualification of Equipment Considering Superheat Effects of high-energy Line Breaks for Plants,Per IE Info Notice 84-90 ML20148J7351988-01-15015 January 1988 SER of First 10-yr Inservice Testing Program Plan & Requests for Relief from Requirements Concluding That Program as Modified by SER Provides Reasonable Assurance of Operational Readiness of safety-related Pumps & Valves ML20237D7591987-12-16016 December 1987 Safety Evaluation Concluding That Util Proposed ATWS Design in Compliance w/10CFR50.62 & Acceptable,Subj to Final Resolution of Tech Spec Issue & Completion of Certain Human Factors Engineering Reviews ML20236R3241987-11-12012 November 1987 Safety Evaluation Supporting Util Submittal of Rev 2 to First 10-yr Interval Inservice Insp Program Plan ML20205Q7131987-04-0101 April 1987 Safety Evaluation Re Util 861001 Submittal of Analysis of Large Break LOCA in Response to License Condition 2.C.(12). Analysis Acceptable & License Condition 2.C.(12) Satisfied ML20211P1991986-12-15015 December 1986 Safety Evaluation Supporting Util 860123 Response to PTS Rule.Matl Properties & Fast Neutron Fluence Calculations Acceptable Until End of Current License.Reevaluation of Rt (PTS) Required by 10CFR50.61 ML20214W8821986-12-0202 December 1986 Safety Evaluation Supporting Util 850524,1104 & 861105 Submittals Re Process Used to Identify Deviations from Emergency Response Guidelines.Justification Provided for Identifying Deviations Acceptable ML20215K9841986-10-22022 October 1986 SER Supporting Util 831115 & 860812 Responses to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Re post-maint Testing Requirements for safety-related Components,Based on Plans to Address Diesel Generator Testing Concerns ML20236N9221986-10-0707 October 1986 SER Accepting Util 840229 & 860529 Responses to Generic Ltr 83-28,Items 3.1.1 & 3.1.2 Re post-maint Testing of Reactor Trip Sys Components ML20215D8321986-10-0707 October 1986 SER Re Util 840229 & 860529 Responses to Generic Ltr 83-28, Items 3.2.1 & 3.2.2 Re post-maint Testing of safety-related components.Post-maint Testing Program Acceptable ML20215D6221986-10-0707 October 1986 SER Re Licensee Response to Generic Ltr 83-28,Item 4.5.1, Reactor Trip Sys Reliability (Sys Functional Testing). Reactor Trip Sys Functional Testing Acceptable ML20203G5361986-07-24024 July 1986 Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Item 1.2 Re post-trip Review Data & Info Capability ML20211P9321986-07-21021 July 1986 Safety Evaluation Supporting Util Preventive Maint Program for Reactor Trip Breakers in Response to Generic Ltr 83-28 Items 4.1,4.2.1 & 4.2.2 ML20134F5061985-08-16016 August 1985 Safety Evaluation Supporting Util 850522 Description of Mods to Low Temp Overpressure Protection Sys of Rcs.Requirements of License Condition 2.C.(13) Met ML20134F5191985-08-16016 August 1985 Safety Evaluation Supporting Rev 12 to Facility Site Addendum Re Removal of 345 Kv Offsite Transmission Line to West Gardner Switching Station from Design ML20128Q8371985-07-0303 July 1985 SER Supporting Deletion of Pseudo Rod Cluster Control Assembly Drop Test at 50% Power.No Useful Info Would Be Gained from Performance of Test ML20128C8321985-06-26026 June 1985 SER Supporting Licensee Programs Re Generic Ltr 83-28,Item 1.1, Post-Trip Review 1999-09-02
[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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hg UNITED STATES
, [ g NUCLEAR REGULATORY COMMISSION g j WASHINGTON, D. C. 20555
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION CIESEL GENERATOR CIRCUIT BREAKER MANUAL CLOSE CAPABILITY KANSAS GAS & ELECTRIC LOMPANY KANSAS CITY POWER AND LIGHT COMPANY KANSAS ELECTRIC POWER COOPERATIVE, INC.
WOLF CREEK GENERATING STATION DOCKET NO. 50-482 INTRODUCTION As the result of an October 14, 1987 occurrence at Wolf Creek Generating Station the staff became aware that manual operation of the diesel generator circuit breakers from the control room was not how it had always assumed.
During the October 14, 1987 occurrence,the control room operators intentionally tripped a diesel generator circuit breaker after the diesel generator had been supplying power to the safety bus. When the operators were ready to reestablish power to the bus from the diesel generator they found that they could not reclose the diesel generator circuit breaker from the control room. It was later detemined that the reason the breaker could not be reclosed from the control room was that the automatic close circuitry used to close the breaker after the diesel generator comes up to speed and voltcge was maintaining a constant close signal to the breaker, and the circuit breaker "anti-pump" circuit was therefore preventing reclosure of the breaker.
Following its own review of the diesel generator circuit breaker close circuits.
the staff found that the circuit breaker also could not be manually closed from the control room unless the diesel generator bus was already energized by one of the offsite circuits. Apparently the reason for this was that the close switch was only intended to be the means of closing the diesel generator circuit breaker when the diesel generator was to be paralleled with the offsite power system. The staff felt that the lack of the above capabilities to marually close the diesel generator circuit breaker from the control room may be contrary to the guidance provided in R.G. 1,62 ("Manual Initiation of Protective Devices") and IEEE Standard 279-1971 ("Criteria for Protection Systems for Nuclear Power Generating Stations").
BACKGROUND IEEE 279 and R.G. 1.62 require that manual initiation of each protective action shall be provided at the system level. It can be argued that manual actuation of the diestl generator circuit breaker is a manual initiation at the component 8806170165 880601 "
PDR ADOCK 05000482 P PDR.
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level rather than the system level and is therefore not required by the above position to be located in the control roem. Capability is provided in the Wolf Creek control roon to manually start the diesel generator which would then automatically close its output circuit breaker onto a dead safety bus when the diesel generator comes up to rated speed and voltage. Offsite power can be separated from the safety bus by manually tripping the offsite breaker from the control room. This action would initiate operation of the loss of voltage relays, subsequent start of the diesel generator, and automatic closing of the diesel generator breaker. Either of the above two described operations (manual diesel generator start or tripping offsite pcwer) could be considered manual initiation capabilities of the standby power system and would therefore meet the IEEE 279 and R.G.1.62 requirements for manual initiation at the system level.
Position C 4 of R.G.1.62 however, also recomends that the amount of equipment cormon to both manual and automatic initiation ba kept to a minimum. It states that it is preferable to limit such common equipment to the final actuation de-vices and the actuated equipment. It does allow however that, action-sequencing functions and interlocks associated with the final actuation devices and actuated equipment may be comron if individual manual initiation at the component level is provided in the control room. At Wolf Creek the two systen level manual ini-tiations of the standby power system described in the above paragraph utilire the same circuit breaker control circuits as used for an autcmatic start of standby power. Position C.4 of R.G. 1,62 therefore recommends in this case that a manual initiation capability at the component level be proviaed in the control rocm for the diesel generator circuit breakers.
EVALUATION Wolf Creek Nuclear Operating Corporation (WCNOC) provided the staff with a preliminary design modification of the diesel generator circuit breaker close l circuitry. The modification was intended to allow the operator to reclose the l circuit breaker from the control room following a manual trip of the breaker, and to allow the operator to close the circuit breaker from the control rocm if it failed to autoi..atically close following a loss of offsite power and automatic start of the diesel generator.
To allow reclosure of the circuit breaker from the control room after it has been mar.ually tripped, the preliminary design modification inserted two contacts into the circuit breaker close circuitry from the circuit breaker control switch located in the control room. These contacts open whenever the control switch is moved from the norcal position. This acts to interrupt the close signal to the circuit breaker ,
and reset the anti-pump circuit when the operator noves the control switch to the l "trip" position. In order to maintain the circuit breaker in the tripped condition I the operator must put the switch in the "pull to lock" position. Following return of the switch to the normal position the close circuit will be reestablished and, with the anti-pump circuit reset, the circuit breaker will close if all the close permissives continue to he satisfied. The staff found that this portion of the modification provided enhanced manual cperation of the circuit breaker from the control room with only minor modification of the control circuitry and was acceptable.
s The preliminary design modification also included changes intended to allow the operator to close the circuit breaker from the control room if it failed to automatically close following a loss of offsite power and automatic start of the diesel generator. This portion of the modification added the following to the close circuit: an additional time delay relay, additional interlocks with the offsite power supply circuit breakers, additional contact from the diesel generator breaker control switch in the control room, additional contact from the diesel engine speed pemissive relay, additional contact from the diesel cenerator voltage pennissive relay, and an additional contact from the diesel generator transfer switch. The preceding pemissives and interlocks are configured in a circuit that essentially duplicates the automatic close circuit of the diesel generator breaker but with the addition of a close contact from the breaker control switch located in the control room. This circuit would allow the operator to manually close the diesel generator breaker from the I control roon if the same permissives and interlocks are satisfied that must be !
satisfied to autcmatically close the breaker. Because the pemissives and l interlocks used in the manual circuit are for the most part simply additional contacts off the same devices used in the automatic circuit it is likely that, if the automatic circuit fails to operate, the manual circuit will be inoperable also. The staff therefore found that this portion of the modification provided only minimal enhancement of the circuit breaker manual capability and required a rather extensive addition to the control circuit wiring.
The alternatives to the above approach are to provide a manual close capability in the control rocm with no permissives or interlocks, or to provide completely separace devices for all the pemissives and interlocks in the manual close cir-cuit. The first alternative would provide no protection against operator error and the second alternative would add additional complexity without a commensurate improvement in safety. Without this portion of the modification the standby power system at Wolf Creek would still meet the single failure criteria, the operator could reclose the diesel generator breaker from the control room if he himself tripped it, and the breaker could be closed locally (no pemissives or interlocks in this circuit) if it failed to close automatically. The staff therefore con-cluded that, although cecommended by position C.4 of R.G. 1.62, this portion of the modification should not be required and could be deleted by WCNOC if it so wished.
By letter dated April 18, 1988, WCNOC submitted the drawings for the final design modification of the diesel generator output breaker control circuitry at Wolf Creek Generating Station. These drawings show the modification required to allow the operator to reclose the diesel generator breaker from the control room following a manual trip of the breaker. However, a sinole contact from the breaker control switch in the control room has been used in the final design rather than the two contacts shown in the preliminary design modification for this circuit. The ope-ration of the manual close function however remains the same as that provided in the preliminary design. This is acceptable.
WCH0C chose to delete the portion of the modification which utilized the various diesel generator interlocks and permissives. As discussed previously this is
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. 4 l
also acceptable, however instructions should be in place informing the operators ;
of the possibility of closing the diesel generator circuit breaker from the 1 local control station if it fails to close automatically. Because this local l manual control does not have the interlocks and permissives associated with the automatic closing circuit, the instructions should warn of the need to verify these parameters manually prior to closing the switch.
CONCLUSION The staff has reviewed the existing and the proposed modifications to the manual close circuitry of the diesel generator circuit breakers at Wolf Creek and has the following conclusions:
- a. If sufficient independence cannot be maintained between automatic initiation and system level manual initiation capabilities of a pro-tective action, position C.4 of R.G.1.62 recommends that manual initiation at the component or channel level be provided in the l control room. As applied to the diesel generator circuit breakers l at Wolf Creek however, the staff concludes that when the concerns )
over operator error and undue complexity are considered there is little benefit to be gained from implementing that portion of the manual modification addressed in item "c" below. ,
1
- b. That portion of the modification that accomplishes reset of the breaker "anti-pump" circuit provides enhanced manual operation of the diesel generator breaker from the control room with only minor modification of the control circuitry and is acceptable. l
- c. That portioni of the preliminary design modification that utilizes i various diesel generator interlocks and permissives, provides only '
minimal enhancement of the circuit breaker manual capability and requires a rather extensive addition to the control circuit. That portion of the modification, although recommended by position C.4 of R.G. 1.62, may therefore be deleted. WCNOC in fact deleted this from their final design modification package,
- d. Instructions should be in place informing the operators of the possi-bility of closing the diesel generator breaker from the local control station if it fails to close automatically. Because this manual cir-cuit does not have the interloch and permissives associated with the automatic closing circuit, the in W uctions should warn of the need to verify these parameters manually prior to closing the switch.
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