ML20138B467
| ML20138B467 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 03/21/1986 |
| From: | KANSAS GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20138B452 | List: |
| References | |
| KMLNRC-86-012, KMLNRC-86-12, NUDOCS 8603250072 | |
| Download: ML20138B467 (6) | |
Text
ENCLOSURE TO KMLNRC 86-049 8603250072 860321 PDR ADOCK 05000482 P
Enclorura to KMLNRC 86-049 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 load sequencer relay driver cards.
In addition, all active l 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 Commision.
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 operation remains unchanged.
The plant design bases, safety limits, limiting safety system settings and limiting conditions for operation also remain unchanged, i
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 System 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 i
exception of the loose parts sensors.
In addition, the system is installed with a remote device to check the response of the system on a few channels to audible signals. This system 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 System and avoid or mitigate damage to Reactor Coolant System components.
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 consegrenses 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.
Enclosure to KMLNRC 86-049 Mr. H.R. Denton Attachment II of KMLNRC 86-012 Page 2 of 6 l
s l
T.S. 4.5.2.e ECCS 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 load sequencer relay driver cards.
In addition all active l pumps and valves related to the specification are subj ected 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 Commission.
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 operation remains unchanged.
The plant design bases, safety limits, limiting safety sye'em settings and limiting conditions for operation also remain unchanged.
Based on the above, this change does not involve a significant increase in the probaoility 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 Containment Spray Actuation Test Signal l
l 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 load sequencer relay driver cards.
In addition, all active l l
pumps and valves related to the specification are subjected to inservice l
l testing performed in accordance with Section XI of the ASME Boiler and l
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 Commission.
l System design features such as redundancy and diversity, including manual initiation of the systems and their individual components, provide an l
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 system settings and limiting conditions for operation also remain unchanged.
l l
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.
Encloture to KMLNRC 86-049 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 load sequencer relay driver cards.
In addition all active l pumps and valves related to the specification are subj ected 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 Commission.
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 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 pre viously evaluated; or create the possibility of a new or different kind of accident f rom any accident previously evaluated; or involve a significant reduction in a margin of safety.
T.S.4.6.2.3.b Containment 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 load sequencer relay driver cards.
In addition all active l pumps and valves related to the specification are subj ected 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 Commission.
~
System design features such as redundancy and diversity, including manual initiation of
- he 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 system settings and limiting e..ditions 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.
k
EncloTure to KMLNRC 86-049 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 l
circuit is tested on a periodic basis between 18-month intervals.
In addition, all active valves related to the specification are subj ect to subjected to inservice testing performed in accordance with Section XI of the ASHE 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 Commission.
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 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 dif fe rent 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 load sequencer relay driver cards.
In addition s11 active l
pumps and vaives 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 Commission.
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 or.erability 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 baces, 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.
L
i e s I
r Enclosura to KMLNRC 86-049 Mr. H.R. Denton
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Attachment II of KMLNRC 86-012 Page 5 of 6 l
1 T.S. 4.7.4.b Essential Service Water Actuation on Safety Injection Signal Through the process of overlap testing, each of the compcnents in this circuit is tested on a periodic basis between 18-month intervals, with the exception of thezload sequencer relay driver cards.
In addition all active pumps and val'ves related to the specification are subjected ' t'o 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 sritten relief has been granted by the Nuclear Regulatory Commisison.
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 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 coasequenses 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. 4.7.7.d.3 Emergency Exhaust 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. l Additionally, system design features such as redundancy and diversity, including manual initiation of the syatems and their individual components, provide an alternate means to assure system operability should an undetectable failure occur during the extended surveillance interval.
The overall reliability of the Emergency Exhaust System has been further substantiate by four actuations of this feature during plant operation.
t There is no design change involved and the method and manner of plant operation remains unchanged.
The plant design bases, safety limits, limitir.g 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.
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