ML17284A580: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
 
(Created page by program invented by StriderTol)
 
(2 intermediate revisions by the same user not shown)
Line 3: Line 3:
| issue date = 10/24/1988
| issue date = 10/24/1988
| title = Application for Amend to License NPF-21,revising Tech Spec Table 3.3.7.1-1 Re Radiation Monitoring Instrumentation to Reflect Mods in Sys Configuration & Operation.Fee Paid
| title = Application for Amend to License NPF-21,revising Tech Spec Table 3.3.7.1-1 Re Radiation Monitoring Instrumentation to Reflect Mods in Sys Configuration & Operation.Fee Paid
| author name = SORENSEN G C
| author name = Sorensen G
| author affiliation = WASHINGTON PUBLIC POWER SUPPLY SYSTEM
| author affiliation = WASHINGTON PUBLIC POWER SUPPLY SYSTEM
| addressee name =  
| addressee name =  
Line 14: Line 14:
| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS
| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS
| page count = 9
| page count = 9
| project =
| stage = Request
}}
}}


=Text=
=Text=
{{#Wiki_filter:AQ CFMRATED DIS IBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DXSTRXBUTXON SYSTEM (RIDS)ACCESSION NBR:8811040304 DOC.DATE 88/10/24 NOTARIZED:
{{#Wiki_filter:AQ CFMRATED           DIS     IBUTION       DEMONSTRATION             SYSTEM REGULATORY INFORMATION DXSTRXBUTXON SYSTEM (RIDS)
YES DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washin'gton Public Powe 05000397 AUTH.NAME AUTHOR AFFILIATION 1 SORENSEN,G.C.
ACCESSION NBR:8811040304         DOC.DATE 88/10/24       NOTARIZED: YES         DOCKET FACIL:50-397   WPPSS   Nuclear Project, Unit 2, Washin'gton Public Powe 05000397 AUTH. NAME           AUTHOR AFFILIATION                                                 1 SORENSEN,G.C.       Washington Public Power Supply System RECIP.NAME           RECXPXENT AFFILIATION Document Control Branch (Document Control Desk)
Washington Public Power Supply System RECIP.NAME RECXPXENT AFFILIATION Document Control Branch (Document Control Desk)


==SUBJECT:==
==SUBJECT:==
Application for amend to License NPF-21,revising Tech Spec Table 3.3.7.1-1 re radiation monitoring instrumentation.
Application for amend to License NPF-21,revising Tech Spec Table 3.3.7.1-1 re radiation monitoring instrumentation.                         R DISTRIBUTION CODE: AOOID       COPIES RECEIVED:LTR     I ENCL   (   SIZE: 5 44 TITLE: OR Submittal: General Distribution NOTES:                                                                                     D RECIPIENT          COPIES            RECIPIENT           COPIES              S ID CODE/NAME         LTTR ENCL     ID CODE/NAME       ,: LTTR ENCL PD5 LA                    1    0    PD5 PD                  2   2 SAMWORTH,R                1    1 XNTERNAL: ACRS                       6    6    ARM/DAF/LFMB NRR/DEST/ADS 7E           1    1    NRR/DEST/CEB 8H                            D NRR/DEST/ESB 8D          1     1     NRR/DEST/MTB 9H NRR/DEST/RSB 8E          1    1    NRR/DOEA/TSB 11                           D NRR/PMAS/ILRB12          1    1    NUDQGS A,   TRACT OGC/HDS2                  1    0      EG   XLE       Ol                         8 RES/DSIR/EIB              1    1 EXTERNAL: LPDR                      1    1    NRC PDR NSIC                      1    1 S'"
DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR I ENCL (SIZE: 5 44 TITLE: OR Submittal:
                                                                                          'A' NOTE 'IO ALL ''RXDS" RECIPIEPIS:
General Distribution R NOTES: RECIPIENT ID CODE/NAME PD5 LA SAMWORTH,R COPIES LTTR ENCL 1 0 1 1 RECIPIENTID CODE/NAME PD5 PD COPIES ,: LTTR ENCL 2 2 D S XNTERNAL: ACRS NRR/DEST/ADS 7E NRR/DEST/ESB 8D NRR/DEST/RSB 8E NRR/PMAS/ILRB12 OGC/HDS2 RES/DSIR/EIB EXTERNAL: LPDR NSIC 6 6 1 1 1 1 1 1 1 1 1 0 1 1 1 1 1 1 ARM/DAF/LFMB NRR/DEST/CEB 8H NRR/DEST/MTB 9H NRR/DOEA/TSB 11 NUDQGS A, TRACT EG XLE Ol NRC PDR D D 8 S'" NOTE'IO ALL''RXDS" RECIPIEPIS:
PLEASE HELP US TO REIXlCE WASTE.'XRKACI'XHE DOCUMEPZ CXÃZEDL DESK,         D RQGM P1-37 (EXT. 20079) TO ELIMINATE YOUR NAME FROM DISTRIBVTIGN LISTS H)R DOVlMENTS YOU DGNPT NEED)                                       S TOTAL NUMBER OF COPIES REQUIRED: LTTR           25   ENCL   22
PLEASE HELP US TO REIXlCE WASTE.'XRKACI'XHE DOCUMEPZ CXÃZEDL DESK, RQGM P1-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBVTIGN LISTS H)R DOVlMENTS YOU DGNPT NEED)'A'D S TOTAL NUMBER OF COPIES REQUIRED: LTTR 25 ENCL 22 4~\~~WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O.Box 968~3000 George Washington Way~Richland, Washington 99352 October 24, 1988 G02-88-221 Docket 50-397 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Nail Station Pl-137 Washington, D.C.20555 Gentlemen:
 
~ \4    ~ ~
WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968   ~ 3000 George Washington Way ~ Richland, Washington 99352 October 24, 1988 G02-88-221 Docket 50-397 U. S. Nuclear     Regulatory Commission Attn:   Document Control Desk Nail Station Pl-137 Washington, D. C.       20555 Gentlemen:


==Subject:==
==Subject:==
NUCLEAR PLANT NO.2 OPERATING LICENSE NPF-21 REQUEST FOR ANENDl'1ENT TO TECHNICAL SPECIFICATION TABLE 3.3.7.1-1, RADIATION MONITORING INSTRUNENTATION In accor dance with the Code of Federal Regulations, Title 10, Parts 50.90 and 2.101, the Supply System hereby submits a request for amendment to the WNP-2 Technical Specifications.
NUCLEAR PLANT NO. 2 OPERATING LICENSE NPF-21 REQUEST FOR ANENDl'1ENT TO TECHNICAL SPECIFICATION TABLE 3.3.7.1-1, RADIATION MONITORING INSTRUNENTATION In accor dance with the Code of Federal Regulations, Title 10, Parts 50.90 and 2.101, the Supply System hereby submits a request for amendment to the WNP-2 Technical Specifications.           Specifically, the Supply System is requesting that Section 3/4.3.7, Table 3.3.7.1-1,               Radiation Monitoring Instrumentation and associated bases be modified (see Attachment 1) to reflect modifications in system configur ation and operation.         These modifications are necessitated by corrective actions taken to prevent an unanalyzed condition that could result from a LOCA and single failure in the main control room ventilation system.
Specifically, the Supply System is requesting that Section 3/4.3.7, Table 3.3.7.1-1, Radiation Monitoring Instrumentation and associated bases be modified (see Attachment 1)to reflect modifications in system configur ation and operation.
Attachment   2   provides   a schematic of the main control room ventilation system as originally   designed     and operated. Should a LOCA have occurred, a single failure could have resulted in both remote intakes remaining closed.               For example, a "hot short" could close an intake valve in one of the remote intakes while the opposite intake was isolated as a result of the LOCA release.                 This event     would have forced the control room ventilation system into                 the "recirculation" mode and caused higher control room in-leakage rates from the loss of control room pressure.
These modifications are necessitated by corrective actions taken to prevent an unanalyzed condition that could result from a LOCA and single failure in the main control room ventilation system.Attachment 2 provides a schematic of the main control room ventilation system as originally designed and operated.Should a LOCA have occurred, a single failure could have resulted in both remote intakes remaining closed.For example, a"hot short" could close an intake valve in one of the remote intakes while the opposite intake was isolated as a result of the LOCA release.This event would have forced the control room ventilation system into the"recirculation" mode and caused higher control room in-leakage rates from the loss of control room pressure.This could in tur n have caused excessive radiation exposure to the control room personnel.
This could in tur n have caused excessive radiation exposure to the control room personnel.     The Supply System is currently analyzing the resultant exposure levels in support of this issue. To avoid this situation, the Supply System has replaced the motor operators on intake valves 51A, 51B, 52A and 52B with manual operators.
The Supply System is currently analyzing the resultant exposure levels in support of this issue.To avoid this situation, the Supply System has replaced the motor operators on intake valves 51A, 51B, 52A and 52B with manual operators.
This is shown in Attachment 3. As a result of the loss of the trip function, the system is operating currently in the "pressurized" mode per the technical specification action statement. This lineup given the discussed scenario ensures exposures   are maintained within the curr ent analyzed conditions.                   With the actuators removed, the "trip" setpoint             listed in Table 3.3.7.1-1 has only an alarm function.
This is shown in Attachment 3.As a result of the loss of the trip function, the system is operating currently in the"pressurized" mode per the technical specification action statement.
SSii040304 SSi02405000397 PDR   ADOCK PDC
This lineup given the discussed scenario ensures exposures are maintained within the curr ent analyzed conditions.
 
With the actuators removed, the"trip" setpoint listed in Table 3.3.7.1-1 has only an alarm function.SSii040304 SSi024 PDR ADOCK 05000397 PDC t Page Two RE/VEST FOR AMENDMENT TO TECHNICAL SPECIFICATION TABLE 3.3.7.1-1, RADIATION MONITORING INSTRUMENTATION With the approval of this Technical Specification change request, operation in the pressurized mode would not be required.Normal plant lineup would be such that the two remote intakes will be administratively controlled open with normal control room intake through those intakes and the normal intake.Occasionally one remote intake might be isolated to facilitate maintenance or other activities.
Page Two t
The 750 cfm exhaust fan would remain operational.
RE/VEST FOR AMENDMENT TO TECHNICAL SPECIFICATION TABLE 3.3.7.1-1, RADIATION MONITORING INSTRUMENTATION With the approval of       this Technical Specification change request, operation in the pressurized mode would not be required. Normal plant lineup would be such that the two remote intakes will be administratively controlled open with normal control room intake through those intakes and the normal intake.
This alignment is shown in Attachment 4.In the event of an FAZ signal, the normal intake will close, the 750 cfm exhaust de-energize, and the emergency filters automatically placed in service.These FAZ initiated actions are per the original plant design and we<e not altered.After the FAZ initiation, either intake can be manually isolated locally, given a change in radiological conditions as sensed by the original radiation elements.This is similar to the original design concept that manually repositioned a remote air intake valve open following an FAZ condition and provided a single isolation given changing radiological conditions.
Occasionally one remote intake might be isolated to facilitate maintenance or other activities.       The 750 cfm exhaust fan would remain operational.           This alignment is shown in Attachment 4. In the event of an FAZ signal, the normal intake will close, the 750 cfm exhaust de-energize, and the emergency filters automatically placed in service.             These FAZ initiated actions are per the original plant design and we< e not altered.
Evaluations and actual plant walk through demonstration have verified that the manual action can be accomplished well within the time frame evaluated in Section 6.4.4 of the WNP-2 FSAR.That is, no operator manipulation of the valve within three hours of the release.Additionally, with both intakes normally open versus one as discussed in the FSAR analysis, the dose to the operators is diluted during the three hour period and consequently is bounded conservatively by the analysis provided in the FSAR.The pur ge valve function also functions similarly and is opened depending on the position of its associated remote intake isolation valve.The proposed changes in the action statement (page 3/4 3-59)are for consistency with other technical specification alarm action statements wherein compensatory measures are taken (in this case manual isolation within one hour)to provide assurance that given an actual alarm condition the plant is aligned to minimize the impact of the event.For example, the 30-day action statements associated with radioactive effluent monitoring allow release to continue provided adequate sampling (a compensatory measure)is performed and action taken on out of specification samples to minimize impact.The present action statement is overly restr ictive given the ability to easily impose compensatory measures.The design safety analysis completed for changing from automatic to manual operators concluded that no new type of event important to safety is created by this change.A failure mode and effects analysis completed for the affected components confirms this conclusion.
After the   FAZ   initiation, either intake can be manually isolated locally, given a   change   in radiological conditions as sensed by the original radiation elements.       This is similar to the original design concept that manually repositioned a remote air intake valve open following an FAZ condition and provided a single           isolation given changing radiological conditions.
The changes ensure that the emergency filtration system remains in service and tha't no single component failure can prevent operator action from establishing a suitable source of air for the pressurization mode.Further, the changes retain the indication function of the remote radiation monitors.
Evaluations and actual plant walk through demonstration have verified that the manual action can be accomplished well within the time frame evaluated in Section 6.4.4 of the WNP-2 FSAR.             That is, no operator manipulation of the valve within three hours of the release.                 Additionally, with both intakes normally open versus one as discussed in the FSAR analysis, the dose to the operators is diluted during the three hour period and consequently is bounded conservatively by the analysis provided in the FSAR. The pur ge valve function also functions similarly and is opened depending on the position of its associated remote intake isolation valve.
Page Three REQUEST FOR AMENDMENT TO TECHNICAL SPECIFICATION TABLE 3.3.7.1-1, RADIATION MONITORING INSTRUMENTATION 1 f i The Supply System has reviewed this proposed change per 10CFR50.59 and concluded that in order.to operate with ,the control room filtration system not in the pressurization mode, the attached technical specification amendment is required.The Supply System has also evaluated this request per 10CFR50.92 and provides the following in support of,a finding for no significant hazards consideration.
The   proposed changes       in the action statement (page 3/4 3-59) are for consistency with other technical specification alarm action statements wherein compensatory measures are taken (in this case manual isolation within one hour) to provide assurance that given an actual alarm condition the plant is aligned to minimize the impact of the event. For example, the 30-day action statements associated with radioactive effluent monitoring allow release to continue provided adequate sampling (a compensatory measure) is performed and action taken on out of specification samples to minimize impact. The present action statement is overly restr ictive given the ability to easily impose compensatory measures.
This change does not: 1)Involve a significant increase in the probability of an accident previously evaluated because the system has no accident preventive function;only accident mitigation.
The   design safety analysis         completed   for changing from automatic to manual operators concluded that no       new type of event important to safety   is created by this   change. A failure   mode and effects analysis completed for     the affected components confirms this conclusion.             The changes ensure that the emergency filtration   system remains     in service   and tha't no single component failure can prevent operator       action from establishing a suitable source of air for the pressurization mode.       Further, the changes retain the indication function of the remote radiation monitors.
The consequences of an accident previously analyzed are not increased because the original FAZ isolation featur es are retained and analyses show adequate time exists for manual isolation of a remote intake if required.The remote air intake isolation valves normal operational position will be open and this preserves the post FAZ required posi tion.2)Create the possibility of a new or different kind of accident from any previously evaluated because, as discussed above, the system has only accident mitigation capability.
 
3)Involve a significant reduction in a margin of safety because the control room pressurization function has not been affected, nor has the time operator action to isolate an intake been exceeded.As discussed above, the Supply System considers that this change does not involve a significant hazards consideration, nor is there a potential for significant change in the types or significant increase in the amount of any effluents that may be released offsite, nor does it involve a significant increase in individual or cumulative occupational radiation exposure.Accordingly, the proposed change meets the eligibility criteria for categorical exclusion set forth in 10CFR51.22(c)(9) and therefor e, per 10CFR51.22(b), an environmental assessment of the change is not required.  
Page Three REQUEST FOR AMENDMENT TO TECHNICAL SPECIFICATION TABLE 3.3.7.1-1, RADIATION MONITORING INSTRUMENTATION 1
.~'~~)I III Page Four RE/VEST FOR AMENDMENT TO TECHNICAL SPECIFICATION TABLE 3.3.7.1-1, RADIATION MONITORING INSTRUMENTATION This Technical Specification change has been reviewed and approved by the WNP-2 Plant Operations Committee (POC)and the Supply System Corporate Nuclear Safety Review Board (CNSRB).In accordance with 10CFR170.21, an application fee of one hundred fifty dollars ($150.00)accompanies this request.In accordance with 10CFR50.91, the State of Washington has been provided a copy of this letter.Very truly yours, G.C.Sorensen, Manager Regulatory Programs PLP:lw Attachments cc: C Eschels-EFSEC JB Martin-NRC RV NS Reynolds-BCP8R RB Samworth-NRC DL Williams-BPA/399 NRC Site Inspector-901A k
f i
STATE OF WASHINGTON
The Supply System         has reviewed this proposed change per 10CFR50.59 and concluded that in order       .to operate with ,the control room filtration system not in the pressurization mode, the attached technical specification amendment is required.
),'.)COUNTY OF BENTON)Request for Amend.to TS  
The Supply System has also evaluated this request per 10CFR50.92 and provides the following in support of,a finding for no significant hazards consideration. This change does not:
: 1) Involve a       significant increase         in the probability of an accident previously evaluated because         the system has no accident preventive function; only accident mitigation.         The consequences       of an accident previously analyzed are not increased because the original FAZ isolation featur es are retained and analyses show adequate time exists for manual isolation of a remote intake             if required.
The   remote air intake           isolation valves normal operational position will be open and this preserves           the post FAZ required posi tion.
: 2) Create     the   possibility of         a   new or different   kind of accident from any previously     evaluated     because,   as discussed above, the system has only accident mitigation capability.
: 3) Involve   a   significant reduction in         a margin of safety because the control room pressurization       function   has   not been affected, nor has the time operator action to isolate an intake been exceeded.
As discussed   above, the Supply System considers that this change does not involve a significant     hazards consideration, nor is there a potential for significant change in the types or significant increase in the amount of any effluents that may be released offsite, nor does           it involve a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed change meets the eligibility criteria for categorical exclusion set forth in 10CFR51.22(c)(9) and therefor e, per 10CFR51.22(b), an environmental assessment of the change is not required.
 
. ~       ' ~ ~
    )I III
 
Page Four RE/VEST FOR AMENDMENT TO TECHNICAL SPECIFICATION TABLE 3.3.7.1-1, RADIATION MONITORING INSTRUMENTATION This Technical Specification change has been reviewed and approved by the WNP-2 Plant Operations Committee (POC) and the Supply System Corporate Nuclear Safety Review Board (CNSRB).
In accordance with 10CFR170.21, an application fee of one hundred     fifty dollars
($ 150.00) accompanies this request. In accordance with 10CFR50.91, the State of Washington has been provided a copy of this letter.
Very truly yours, G. C. Sorensen, Manager Regulatory Programs PLP:lw Attachments cc:   C   Eschels   EFSEC JB Martin   NRC RV NS Reynolds - BCP8R RB Samworth   NRC DL Williams - BPA/399 NRC Site Inspector - 901A
 
k Request for Amend. to TS STATE OF WASHINGTON    ),'                   


==Subject:==
==Subject:==
Radiation Monitoring Instrumentation I, A.G.HOSLER, being duly sworn, subscribe to and say that I am the Manager, WNP-2 Licensing, for the WASHINGTON PUBLIC POWER SUPPLY SYSTEM, the applicant herein;that I have full authority to execute this oath;that I have reviewed the foregoing; and that to the best of my knowledge, information and belief the statements made in it are true.DATE Om~c 6~v&#x17d;~"/, 1988 A.G.HOSLER, Manager WNP-2 Licensing On this day personally appeared before me A.G.HOSLER to me known to be the individual who executed the foregoing instrument and acknowledged that he signed the same as his free act and deed for the uses and purposes herein mentioned.
Radiation Monitoring Instrumentation
GIVEN under my hand and seal this~~$day of ,1988.Notary u ic in and for the State of Washington Residing at  
                      .)
~~L f f}}
COUNTY OF BENTON        )
I, A. G. HOSLER, being     duly sworn, subscribe to and say that I am the Manager, WNP-2 Licensing, for the WASHINGTON PUBLIC POWER SUPPLY SYSTEM, the applicant herein; that I have full authority to execute this oath; that I have reviewed the foregoing; and that to the best of my knowledge, information and belief the statements made in it are true.
DATE   Om~c 6~v'    ~"/,       1988 A. G. HOSLER, Manager WNP-2   Licensing On this day personally appeared       before me A. G. HOSLER to me known to be the individual   who   executed   the foregoing instrument and acknowledged that he signed the   same   as his free act and deed for the uses and purposes herein mentioned.
GIVEN under my hand and     seal   this ~~$     day of                     ,1988.
Notary u ic in and       for the State of Washington Residing at
 
      ~ ~
L f f}}

Latest revision as of 06:57, 10 November 2019

Application for Amend to License NPF-21,revising Tech Spec Table 3.3.7.1-1 Re Radiation Monitoring Instrumentation to Reflect Mods in Sys Configuration & Operation.Fee Paid
ML17284A580
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 10/24/1988
From: Sorensen G
WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML17284A581 List:
References
GO2-88-221, NUDOCS 8811040304
Download: ML17284A580 (9)


Text

AQ CFMRATED DIS IBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DXSTRXBUTXON SYSTEM (RIDS)

ACCESSION NBR:8811040304 DOC.DATE 88/10/24 NOTARIZED: YES DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washin'gton Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION 1 SORENSEN,G.C. Washington Public Power Supply System RECIP.NAME RECXPXENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Application for amend to License NPF-21,revising Tech Spec Table 3.3.7.1-1 re radiation monitoring instrumentation. R DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR I ENCL ( SIZE: 5 44 TITLE: OR Submittal: General Distribution NOTES: D RECIPIENT COPIES RECIPIENT COPIES S ID CODE/NAME LTTR ENCL ID CODE/NAME ,: LTTR ENCL PD5 LA 1 0 PD5 PD 2 2 SAMWORTH,R 1 1 XNTERNAL: ACRS 6 6 ARM/DAF/LFMB NRR/DEST/ADS 7E 1 1 NRR/DEST/CEB 8H D NRR/DEST/ESB 8D 1 1 NRR/DEST/MTB 9H NRR/DEST/RSB 8E 1 1 NRR/DOEA/TSB 11 D NRR/PMAS/ILRB12 1 1 NUDQGS A, TRACT OGC/HDS2 1 0 EG XLE Ol 8 RES/DSIR/EIB 1 1 EXTERNAL: LPDR 1 1 NRC PDR NSIC 1 1 S'"

'A' NOTE 'IO ALL RXDS" RECIPIEPIS:

PLEASE HELP US TO REIXlCE WASTE.'XRKACI'XHE DOCUMEPZ CXÃZEDL DESK, D RQGM P1-37 (EXT. 20079) TO ELIMINATE YOUR NAME FROM DISTRIBVTIGN LISTS H)R DOVlMENTS YOU DGNPT NEED) S TOTAL NUMBER OF COPIES REQUIRED: LTTR 25 ENCL 22

~ \4 ~ ~

WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352 October 24, 1988 G02-88-221 Docket 50-397 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Nail Station Pl-137 Washington, D. C. 20555 Gentlemen:

Subject:

NUCLEAR PLANT NO. 2 OPERATING LICENSE NPF-21 REQUEST FOR ANENDl'1ENT TO TECHNICAL SPECIFICATION TABLE 3.3.7.1-1, RADIATION MONITORING INSTRUNENTATION In accor dance with the Code of Federal Regulations, Title 10, Parts 50.90 and 2.101, the Supply System hereby submits a request for amendment to the WNP-2 Technical Specifications. Specifically, the Supply System is requesting that Section 3/4.3.7, Table 3.3.7.1-1, Radiation Monitoring Instrumentation and associated bases be modified (see Attachment 1) to reflect modifications in system configur ation and operation. These modifications are necessitated by corrective actions taken to prevent an unanalyzed condition that could result from a LOCA and single failure in the main control room ventilation system.

Attachment 2 provides a schematic of the main control room ventilation system as originally designed and operated. Should a LOCA have occurred, a single failure could have resulted in both remote intakes remaining closed. For example, a "hot short" could close an intake valve in one of the remote intakes while the opposite intake was isolated as a result of the LOCA release. This event would have forced the control room ventilation system into the "recirculation" mode and caused higher control room in-leakage rates from the loss of control room pressure.

This could in tur n have caused excessive radiation exposure to the control room personnel. The Supply System is currently analyzing the resultant exposure levels in support of this issue. To avoid this situation, the Supply System has replaced the motor operators on intake valves 51A, 51B, 52A and 52B with manual operators.

This is shown in Attachment 3. As a result of the loss of the trip function, the system is operating currently in the "pressurized" mode per the technical specification action statement. This lineup given the discussed scenario ensures exposures are maintained within the curr ent analyzed conditions. With the actuators removed, the "trip" setpoint listed in Table 3.3.7.1-1 has only an alarm function.

SSii040304 SSi02405000397 PDR ADOCK PDC

Page Two t

RE/VEST FOR AMENDMENT TO TECHNICAL SPECIFICATION TABLE 3.3.7.1-1, RADIATION MONITORING INSTRUMENTATION With the approval of this Technical Specification change request, operation in the pressurized mode would not be required. Normal plant lineup would be such that the two remote intakes will be administratively controlled open with normal control room intake through those intakes and the normal intake.

Occasionally one remote intake might be isolated to facilitate maintenance or other activities. The 750 cfm exhaust fan would remain operational. This alignment is shown in Attachment 4. In the event of an FAZ signal, the normal intake will close, the 750 cfm exhaust de-energize, and the emergency filters automatically placed in service. These FAZ initiated actions are per the original plant design and we< e not altered.

After the FAZ initiation, either intake can be manually isolated locally, given a change in radiological conditions as sensed by the original radiation elements. This is similar to the original design concept that manually repositioned a remote air intake valve open following an FAZ condition and provided a single isolation given changing radiological conditions.

Evaluations and actual plant walk through demonstration have verified that the manual action can be accomplished well within the time frame evaluated in Section 6.4.4 of the WNP-2 FSAR. That is, no operator manipulation of the valve within three hours of the release. Additionally, with both intakes normally open versus one as discussed in the FSAR analysis, the dose to the operators is diluted during the three hour period and consequently is bounded conservatively by the analysis provided in the FSAR. The pur ge valve function also functions similarly and is opened depending on the position of its associated remote intake isolation valve.

The proposed changes in the action statement (page 3/4 3-59) are for consistency with other technical specification alarm action statements wherein compensatory measures are taken (in this case manual isolation within one hour) to provide assurance that given an actual alarm condition the plant is aligned to minimize the impact of the event. For example, the 30-day action statements associated with radioactive effluent monitoring allow release to continue provided adequate sampling (a compensatory measure) is performed and action taken on out of specification samples to minimize impact. The present action statement is overly restr ictive given the ability to easily impose compensatory measures.

The design safety analysis completed for changing from automatic to manual operators concluded that no new type of event important to safety is created by this change. A failure mode and effects analysis completed for the affected components confirms this conclusion. The changes ensure that the emergency filtration system remains in service and tha't no single component failure can prevent operator action from establishing a suitable source of air for the pressurization mode. Further, the changes retain the indication function of the remote radiation monitors.

Page Three REQUEST FOR AMENDMENT TO TECHNICAL SPECIFICATION TABLE 3.3.7.1-1, RADIATION MONITORING INSTRUMENTATION 1

f i

The Supply System has reviewed this proposed change per 10CFR50.59 and concluded that in order .to operate with ,the control room filtration system not in the pressurization mode, the attached technical specification amendment is required.

The Supply System has also evaluated this request per 10CFR50.92 and provides the following in support of,a finding for no significant hazards consideration. This change does not:

1) Involve a significant increase in the probability of an accident previously evaluated because the system has no accident preventive function; only accident mitigation. The consequences of an accident previously analyzed are not increased because the original FAZ isolation featur es are retained and analyses show adequate time exists for manual isolation of a remote intake if required.

The remote air intake isolation valves normal operational position will be open and this preserves the post FAZ required posi tion.

2) Create the possibility of a new or different kind of accident from any previously evaluated because, as discussed above, the system has only accident mitigation capability.
3) Involve a significant reduction in a margin of safety because the control room pressurization function has not been affected, nor has the time operator action to isolate an intake been exceeded.

As discussed above, the Supply System considers that this change does not involve a significant hazards consideration, nor is there a potential for significant change in the types or significant increase in the amount of any effluents that may be released offsite, nor does it involve a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed change meets the eligibility criteria for categorical exclusion set forth in 10CFR51.22(c)(9) and therefor e, per 10CFR51.22(b), an environmental assessment of the change is not required.

. ~ ' ~ ~

)I III

Page Four RE/VEST FOR AMENDMENT TO TECHNICAL SPECIFICATION TABLE 3.3.7.1-1, RADIATION MONITORING INSTRUMENTATION This Technical Specification change has been reviewed and approved by the WNP-2 Plant Operations Committee (POC) and the Supply System Corporate Nuclear Safety Review Board (CNSRB).

In accordance with 10CFR170.21, an application fee of one hundred fifty dollars

($ 150.00) accompanies this request. In accordance with 10CFR50.91, the State of Washington has been provided a copy of this letter.

Very truly yours, G. C. Sorensen, Manager Regulatory Programs PLP:lw Attachments cc: C Eschels EFSEC JB Martin NRC RV NS Reynolds - BCP8R RB Samworth NRC DL Williams - BPA/399 NRC Site Inspector - 901A

k Request for Amend. to TS STATE OF WASHINGTON ),'

Subject:

Radiation Monitoring Instrumentation

.)

COUNTY OF BENTON )

I, A. G. HOSLER, being duly sworn, subscribe to and say that I am the Manager, WNP-2 Licensing, for the WASHINGTON PUBLIC POWER SUPPLY SYSTEM, the applicant herein; that I have full authority to execute this oath; that I have reviewed the foregoing; and that to the best of my knowledge, information and belief the statements made in it are true.

DATE Om~c 6~v' ~"/, 1988 A. G. HOSLER, Manager WNP-2 Licensing On this day personally appeared before me A. G. HOSLER to me known to be the individual who executed the foregoing instrument and acknowledged that he signed the same as his free act and deed for the uses and purposes herein mentioned.

GIVEN under my hand and seal this ~~$ day of ,1988.

Notary u ic in and for the State of Washington Residing at

~ ~

L f f