ML20137L647
| ML20137L647 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 01/20/1986 |
| From: | Koester G KANSAS GAS & ELECTRIC CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20137L651 | List: |
| References | |
| KMLNRC-86-012, KMLNRC-86-12, NUDOCS 8601280047 | |
| Download: ML20137L647 (14) | |
Text
. 4 KANSAS GAS AND ELECTRIC COMPANY T&E ELECTFhC COMPANY GLENN L MOESTER victpets.otmi muettam January 20, 1986 Mr. Harold R. Denton Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Contnission Washington, D. C. 20555 KMLNRC 86-012 Re: Docket No. S'IN 50-482 Subj: Revision to Technical Specifications-Eighteen Month surveillance Interval
Dear Mr. Denton:
The purpose of this letter is to transmit three original and 40 conformed copies of an application for Amendment to Facility Operating License No.
NPF-42 for Wolf Creek Generating Station, Unit No. 1.
This application requests that the Wolf Creek Generating Station, Unit No. 1 Technical Specifications, delineated in Attachment I, be revised to allow a one-time only deferment of the eighteen month surveillance interval until Refuel 1. In order to safely perform these surveillances the plant must be in Mode 5 (COLD SIRTIDOWN) or 6 (REFUELING) . The proposed changes to the Technical Specifications are provided as Attachment III.
Refuel 1 is the next scheduled shutdown and is currently scheduled to begin in October, 1986. In the event of any unanticipated delays in the refueling cchedule a unit shutdown to perform these surveillances will be initiated by October 31, 1986. Therefore this request entails an approximate four month extension in the most limiting case. If an unscheduled shutdown of sufficient duration and resulting in appropriate plant conditions occurs prior to Refuel 1, Kansas Gas and Electric Company intends to perform any surveillances that can reasonably be completed. Since refueling outages normally occur approximately every twelve to eighteen months, extensions beyond the eighteen month plus twenty five percent maximum interval allowed by the Technical Specifications are not usually necessary. However, due to the extended plant startup program and plant performance during Cycle 1, Kansas Gas and Electric Conpany is requesting the aforementioned Technical Specification Revisions. Without the requested revisions Wolf Creek Generating Station would be forced into a Mode 5 outage for the purpose of surveillance testing.
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Mr. H. R. Denton KMLNRC 86-012 Page 2 January 20, 1986 This request would also allow the provisions of .%chnical Specification 4.0.2 to be reset to allow the necessary interval tolerances to perform subsequent surveillances.
The requested revisions would not have a significant inpact on safe
- operations of the plant when conpared to the transient associated with a shutdown for the purpose of performing these surveillances. A canplete Safety Evaluation and Significant Hazards Consideration are provided as Attachments I and II respectively.
In accordance with 10 CPR 50.91, a copy of this applicaiton, with Attactinents, is being provided to the designated Kansas State Official.
Enclosed is a check (No. 67588) for the S150.00 application fee required by 10 CFR 170.21.
If you have any questions concerning this matter, please contact me or Mr.
j O.L. Maynard of my staff.
Very truly yours, yy f A Glenn L. Koester Vice President - Nuclear GLK:see Enclosure AttaclYnents: I-Safety Evaluation II-Significant Hazards Consideration III-Proposed Technical Specification Changes i
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STATE OF KANSAS )
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Glenn L. Koester, of lawful age, being first duly sworn upon oath says that he is Vice President - Nuclear and an Offiew. of Kansas Gas and Electric Company; that he has read the foregoing document and knows the content thereof; that he has executed the same for and on behalf of said Company with full Power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.
I By Glenn L. Koeste'r Vice President - Nuclear SUBSCRIBED and sworn to before me this 20th day of January , 1986
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Mr. H.R. Denton Attachment I of KMLNRC 86-012 Page 1 of 2 SAFETY EVAWATION This application requests that the Wolf Creek Generating Station, Unit No. 1 Technical Specifications listed below be revised to allow a one-time only deferment of the eighteen month surveillance interval until Refuel 1. In order to safely perform these surveillances the plant nust be in Mode 5 (COLD SHU'IDOWN) or 6 (REEUELING) . The proposed changes to the Technical Specifications are provided as Attachment III.
Refuel 1 is the next scheduled shutdown and is currently scheduled to begin in October, 1986. In the event of any unanticipated delays in the refueling schedule a unit shutdown to perform these surveillances will be initiated by Octber 31, 1986. Therefore this request entails an approximate four month extension in the most limiting case. If an unscheduled shutdown of sufficient duration and resulting in appropriate plant conditions occurs prior to Refuel 1, Kansas Gas and Electric Conpany intends to perform any surveillances that can reasonably be completed. Since refueling outages normally occur approximately every twelve to eigtheen months, extensions beyond the eighteen month plus twenty five percent maximm interval allowed by the Technical Specifications are not usually necessary. However, due to the extended plant startup program and plant performance during Cycle 1, Kansas Gas and Electric Conpany is requesting the aforementioned Technical Specification Revisions. Without the requested revisions Wolf Creek Generating Station would be forced into a Mode 5 outage for the purpose of surveillance testing.
Tech Spec Page Description 1
4.1.2.2.b 3/4 1-8 Boration Valve Actuation on Safety Injection Signal 4.3.3.9.c 3/4 2-62 Channel Calibration Loose Parts Monitoring System 4.5.2.e 3/4 5-5 ECCS Actuation On Safety Injection Signal 4.6.2.1.c 3/4 6-13 Containment Spray Actuation Test 4.6.2.2.c 3/4 6-14 Spray Additive Value Actuation on Safety Injection Signal 4.6.2.3.b '3/4 6-15 Containment Cooling System Actuation On Safety Injection Signal 4.6.3.2 3/4 6-17 Contalment Isolation Signal Test 4.7.3.b 3/4 7-11 Conponent Cooling Water Actuation On Safety Injection Signal 4.7.4.b 3/4 7-12 Essential Service Water Actuation On Safety Injection Signal 4.7.7.d.3 3/4 7-18 Bnergency Exhaust Systen Actuation On Safety Injection Signal
- 4. 8.1.1. 2. f (2-10) 3/4 8-4,8-5,8-6 Diesel Generator Testing 4.8.2.1.d 3/4 8-10 Battery Service Test
Mr. H.R. Denton Attachment II of KMLNRC 86-012 Page 2 of 2 This request would also allow the provisions of W hnical Specification 4.0.2 to be reset to allow the necessary interval tolerances to perform subsequent surveillances.
The requested revisions would not have a significant impact on safe operation of the plant when compared to the transient associated with a shutdown for the purpose of performing these surveillances. Based on the above and the considerations presented in Attachment III, the aforementioned proposed revisions to the Wolf Creek Generating Station, Unit No. 1, Technical Specifications do not adversely affect or endanger the health or safety of the general public or involve a significant safety hazard.
9
- Mr. H. R. Denton Attachment II to KMLNRC 86-012 Page 1 of 6 SIGNIFICANT HAZARDS CONSIDERATION T.S. 4.1.2.2.b Boration Valve Actuation on Safety Injection Signal Through the process of overlap testing, each of the components in this circuit is tested on a periodic basis between 18-month intervals, with the exception of the Solid State Protection Systen Relays. In addition, all active valves related to the specification are subjected to inservice testing performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a(g),
except where specific written relief has been granted by the Nuclear Regulatory Contnision.
Systen design features such as redundancy aM diversity, including manual initiation of the systems and their individual components, provide an alternate means to assure system operability should an uMetectable failure occur during the extended surveillance interval.
There is no design change involved and the method and manner of plant operation remains unchanged. The plant design bases, safety limits, limiting safety system settings and limiting conditions for operation also remain unchanged.
Based on the above, this change does not involve a significant increase in the probability or consequenses of an accident previously evaluated; or create the possibility of a new or different kind of accident from any accident previously evaluated; or involve a significant reduction in a margin of safety.
T.S. 4.3.3.9.c Channel Calibration Loose Parts Monitoring Systen-Through the process of overlap testing, each of the components in this circuit is tested on a periodic basis between 18-month intervals, with the exception of the loose parts sensors. In addition, the system is installed with a renote device to check the response of the system on a few channels to audible signals. This systen is not safety related or special scope, it serves to ensure that sufficient capability is available to detect loose metallic parts in the Reactor Coolant Systen and avoid or mitigate damage to Reactor Coolant Systen components.
There is no design change involved and the method and manner of plant operation renains unchanged. The plant design bases, safety limits, limiting safety systen settings and limiting conditions for operation also remain unchanged.
Based on the above, this change does not involve a significant increase in the probability or consequenses of an accident previously evaluated; or create the possibility of a new or different kind of accident from any accident previously evaluated; or involve a significant reduction in a margin of safety.
Mr. H.R. Denton Attachment II of KMLNRC 86-012 Page 2 of 6 T.S. 4.5.2.e _ EDCS Actuation on Safety ' Injection Signal Signal Through the process of overlap testing, each of the components in this circuit is tested on a periodic basis between 18-month intervals, with the exception of the Solid State Protection System Relays. In addition all active pumps and valves related to the specification are subjected to inservice testing performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a (g) , except where specific written relief has been granted by. the Nuclear Regulatory Connission.
System design features such as redundancy and diversity, including manual initiation of the systems and their individual components, provide an alternate means to assure system operability should an undetectable failure occur during the extended surveillance interval.
There is no design change involved and the method and manner of plant operatien renains unchanged. The plant design bases, safety limits, limiting safety systen settings and limiting conditions for operation also remain unchanged.
Based on the above, this change does not involve a significant increase in the probability or consequenses of an accident previously evaluated; or create the possibility of a new or different kind of accident from any accident previously evaluated; or involve a significant reduction in a margin of safety.
T.S. 4.6.2.1.c Containnent Spray Actuation Test Signal Through the process of overlap testing, each of the conponents in this circuit is tested on a periodic-basis between 18-month intervals, with the exception of the Solid State Protection Systen relays. In addition, all active pumps and valves related to the specification are subjected to inservice testing performed in accordance with Section XI of the ASME Boiler-and Pressure Vessel Code and applicable addenda as required by 10 CFR Section 50.55a(g), except where specific written relief has been granted by the Nuclear Regulatory Comnission.
System design features such as redundancy and diversity, including manual initiation of the systens and their individual conponents, provide an alternate means to assure systen operability should an undetectable failure occur during the extended surveillance interval.
There is no design change involved and the method and manner of plant operation remains unchanged. The plant design bases, safety limits, limiting safety systen settings and limiting conditions for operation also remain unchanged.
Based on the above, this change does not involve a significant increase in the probability or consequenses of an accident previously evaluated; or create the possibility of a new or different kind of accident from any accident previously evaluated;- or involve a significant reduction in a nargin of safety.
Mr. H.R. Denton Attachment II of KMLNRC 86-012 Page 3 of 6 T.S. 4.6.2.2.c Spray Additive Valve Actuation on Safety Injection Signal Through the process of overlap testing, each of the components in this circuit is tested on a periodic basis between 18-month intervals, with .the exception of the Solid State Protection System Relays. In addition all active pumps and valves related to the specification are subjected to inservice testing performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a (g) , except where specific written relief has been granted by the Nuclear Regulatory Comnission.
System design features such as redundancy and diversity, including manual initiation of the systens and their individual components, provide an alternate means to assure systen operability should an undetectable failure occur during the extended surveillance interval.
There is no design change involved and the method and manner of plant operation remains unchanged. The plant design bases, safety limits, limiting safety systen settings and limiting conditions for operation also renain unchanged.
Based on the above, this change does not involve a significant increase in the probability or consequenses of an accident previously evaluated; or create the possibility of a new or different kind of accident from any accident previously evaluated; or involve a significant reduction in a margin of safety.
T.S.4.6.2.3.b Contairmnent Cooling System Actuation On Safety Injection Signal Through the process of overlap testing, each of the components in this circuit is tested on a periodic basis between 18-month intervals, with the exception of the Solid State Protection' System Relays. In addition all active pumps and valves related to the specification are subjected to inservice testing performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a (g) , except where specific written relief has been granted by the Nuclear Reculatory Comnission.
Systen daign features such as redundancy and diversity, including manual initiation of the systems and their individual components, provide an alternate means to assure system operability should an undetectable failure occur during the extended surveillance interval.
There is no design change involved and the method and manner of plant operation remains unchanged. The plant design bases, safety limits, limiting safety systen settings and limiting conditions for operation also remain unchanged.
Based on the above, this change does not involve a significant increase in the probability or consequenses of an. accident previously evaluated; or create the possibility of a new or different kind of accident from any accident previously evaluated; or involve a significant reduction in a margin of safety.
Mr. H.R. Denton Attachment II of KMLNRC 86-012 Page 4 of 6
- T.S. 4.6.3.2 Containment Isolation Signal Test Through the process of overlap testing, each of the components in this circuit is tested on a periodic basis between 18-month intervals, with the exception of the Solid State Protection System Relays. . In addition, all active valves related to the specification are subjected to inservice testing performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a(g),
except where specific written' relief has been granted by the Nuclear Regulatory Comission.
Systs design features such as redundancy and diversity, including m nual initiation of the systems and their individual components, provide an alternate means to assure systs operability should an undetectable failure occur during the extended surveillance interval.
There is no design change involved and the method and manner of plant operation reains unchanged. The plant design bases, safety limits, limiting safety systs settings and limiting conditions for operation also t
remain unchanged.
Based on the above, this change does not involve a significant increase in the probability or consequenses of an accident previously evaluated; or create the possibility of a new or different kind of accident from any accident previously evaluated; or involve a significant reduction in a margin of safety.
T.S. 4.7.3.b Component Cooling Water Actuation on Safety Injection Signal Through the process of overlap testing, each of the components in this circuit is tested on a periodic basis between 18-month intervals, with the exception of the' Solid State Protection System Relays. In addition all active punps and valves related to the specification are subjected to inservice testing performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a (g) , except where specific written relief has been granted- by the Nuclear Regulatory Comission.
System design features such as redundancy and diversity, including. manual initiation of the systems and their individual components, provide an alternate means to assure systs operability should an undetectable failure occur during the extended surveillance interval.
There is no design change involved and the method and manner of plant operation remains unchanged. The plant design bases, safety limits, limiting safety syst s settings and limiting conditions for operation also remain unchanged.
Based on the above, this change does not involve a significant increase in the probability or consequenses of an accident previously evaluated; or create the possibility of a new or different kind of accident from any accident previously evaluated; or involve a significant reduction in a margin of safety.
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Mr. H.R. Denton Attachment II of KMLNRC 86-012 Page 5 of 6 T.S. 4.7.4.b Essential Service Water Actuation on Safety Injection Signal l
Through the process of overlap testing, each of the conponents in this circuit is tested on a periodic basis between 18-month intervals, with the exception of the Solid State Protection Systen Relays. In addition all
, active pm ps and valves related to the specification are subjected to inservice testing performed in accordance with Section XI of the ASME Boiler
! and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a (g) , except where specific written relief has been granted by the Nuclear Regulatory Conunisison.
l Systen design features such as redundancy and diversity, including manual initiation of the systems and their individual components, provide an alternate means to assure system operability should an' undetectable failure occur during the extended surveillance interval.
There is no design change involved and the method and manner of plant operation renains unchanged. We plant- design bases, safety . limits,
] limiting safety systen settings and limiting conditions for operation also remain unchanged.
L i
Based on the above, this change does not involve a significant increase in j the' probability or consequenses of an accident previously evaluated; or create the possibility of a new or different kind of accident from any accident previously evaluated; or involve a significant reduction in a-margin of safety, i
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T.S. 4.7.7.d.3 Dnergency Exhaust Systen Actuation on Safety Injection Signal 4
' Through the process of overlap testing, each of the conponents in this circuit is tested on a periodic basis between 18-month intervals, with the exception of the Solid State Protection System Relays. Additionally, systen design features such as reduadancy and diversity, including manual initiation of the systems and their individual conponents, provide an alternate means to assure systen operability should an undetectable failure occur during the extended surveillance interval. The overall reliability of
- the Ernergency Exhaust Systen has been further substantiate by four~
actuations of this feature during plant operation.
%ere is no' design change involved and the method and manner of plant
', operation remains unchanged. The plant design bases, safety limits, limiting safety system settings and limiting conditions for operation also remain unchanged.
Based on the above, this change _does not involve a significant increase in the probability or consequenses of an accident previously evaluated; or create the possibility of a new or different kind of accident from any
. accident previously evaluated; or involve a significant reduction in a j margin of safety.
}
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Mr. H.R. Denton Attachment II of KMLNRC 86-012 Page 6 of 6 T.S. 4.8.1.1.2.f (2-10) Diesel Generator Testing Each Standby Diesel Generator is presently being tested monthly to denonstrate its operability and capability to assume load. Portions of the 18-month surveillance [4.8.1.1.2. f.1) , 11) and 12)] have been performed since the initial surveillance on July 23, 1984. Overlapping tests of portions of the Standby Diesel Generator Systen as well as five (5) actuations of the Standby Diesel Generators during plant operation, substantiate overall systen reliability.
Although a single valid test and failure per Regulatory Guide 1.108 occurred during a manual start of Diesel Generator 'A', this failure was directly attributable to a mispositioned governor needle valve concurrent with the addition of oil to the governor as described in Special Report 10. This problem was detected and subsequently corrected as part of the existing periodic diesel testing program delineated in the Technical Specifications.
There is no design change involved and the method and manner of plant operation rennins unchanged. The plant design bases, safety limits, limiting safety systen settings and limiting conditions for operation also remain unchanged.
Based on the above, this change does not involve a significant increase in the probability or consequenses of an accident previously evaluated; or create the possibility of a new or different kind of accident from any accident previously evaluated; or involve a significant reduction in a nargin of safety.
T.S. 4.8.2.1.d Battery Service Test This battery service test verifies specific battery capacity which demonstrates that the battery will meet the design requirenents of the DC system. This test was' initially performed with satisfacotry results, as part of preoperational testing on Novenber 28, 1984.
- Wolf Creek Generating Station is in its first cycle of operation and the batteries are relatively new and no substantial loads have been added to the batteries. Additionally, battery surveillances have been performed weekly or quarterly for electrolyte level, float voltage, specific gravity, total battery terminal voltage, visible corrosion, terminal connection resistance i
and electrolyte temperature. Thus providing a means of identifing potential failures.
There is no design change involved. and the method and manner of plant operation renains unchanged. 'Ihe plant ~ design bases, safety limits, limiting safety systen settings and limiting conditions for operation also renain unchanged.
Based on the above, this change does not involve a significant increase- in the probability or. consequenses of an accident previously' evaluated; or create the possibility of a new or different kind of accident from any accident previously evaluated; or involve a significant reduction in a l margin of safety.
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