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{{#Wiki_filter:p 4C CELE RATED D1FJBUT1 ON DE M ON STR+ON SYSTEM i'EGULATORY XNFORMATION DISTRXBUTION SYSTEM (RIDS)ACCESSION NBR:8904050343 DOC.DATE: 89/03/22 NOTARIZED:
{{#Wiki_filter:p 4C CELE RATED         D1FJBUT1 ON                       DE M ON STR+ON         SYSTEM i'EGULATORY XNFORMATION DISTRXBUTION SYSTEM                                   (RIDS)
NO FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe AUTH.NAME AUTHOR AFFILIATION POWERS,C.M.
ACCESSION NBR:8904050343                       DOC.DATE: 89/03/22   NOTARIZED: NO       DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe                       05000397 AUTH. NAME           AUTHOR AFFILIATION POWERS,C.M.         Washington Public Power Supply System RECIP.NAME           RECIPIENT AFFILIATION MARTIN,J.B.         Region 5, Ofc of the Director
Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION MARTIN,J.B.
Region 5, Ofc of the Director  


==SUBJECT:==
==SUBJECT:==
Special rept:on 890306,post-accident sampling primary coolant radiation monitor inoperable.
Special rept:on 890306,post-accident sampling primary coolant radiation monitor inoperable.
DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR j ENCL+SIZE: TITLE: OR Submittal:
DISTRIBUTION CODE: AOOID TITLE:  OR  Submittal: General Distribution COPIES RECEIVED:LTR j ENCL + SIZE:
General Distribution NOTES: DOCKET 05000397 RECIPIENT ID CODE/NAME PD5 LA SAMWORTH,R INTERNAL: ACRS NRR/DEST/ADS 7E NRR/DEST/ESB 8D NRR/DEST/MTB 9H NRR/DOEA/TSB 1 1 OGC/HDS2 RES/DS XR/EIB EXTERNAL: LPDR NSIC COPIES LTTR ENCL 1 5'1 1 1 1 1 1'ECIPIENT ID CODE/NAME PD5 PD ARM/DAF/LFMB NRR/DEST/CEB 8H NRR/DEST/ICSB NRR/DEST/RSB 8E J)OC~BSTRA~
NOTES:
EG FILE 01 NRC PDR COPXES LTTR ENCL NOTE TO ALL"RIDS" RECIPIENIS'LEASE HELP US K)REMJCE WASTElCXNZACZ'lHE DOCUMEPZ COÃI$OL DESK ROOM Pl-37 (EXT.20079)KO XLIMZLTE YOUR NAME FMM DICTION LISTS POR DOCUMEMIS YOU DCINIT NEZDf TOTAL NUMBER OF COPXES REQUIRED: LTTR 28 ENCL  
RECIPIENT                         COPIES                          COPXES ID PD5 LA CODE/NAME SAMWORTH,R 1'ECIPIENT LTTR ENCL 1
~.
5 '
I~A (..~.2~WASHINGTON PUBLIC POWER SUPPLY SYSQRIVP Sly M'lW 4 1~$P.O.Box 968~3000 George Washington Way~Richland, Washington 99352~I ARZ7 A 9: P3 Docket No.50-39/March 22, 1989 Nr.J.B.Martin Regional Administrator USNRC, Region V 1450 Maria Lane, Suite 210 Walnut Creek, CA 94596
ID PD5 PD CODE/NAME    LTTR ENCL INTERNAL: ACRS                                               ARM/DAF/LFMB NRR/DEST/ADS     7E                   1          NRR/DEST/CEB 8H NRR/DEST/ESB    8D                    1         NRR/DEST/ICSB NRR/DEST/MTB    9H                    1          NRR/DEST/RSB 8E NRR/DOEA/TSB    11                    1            J)OC~BSTRA~
OGC/HDS2                              1          EG FILE     01 RES/DS XR/EIB EXTERNAL: LPDR                                              NRC PDR NSIC NOTE TO ALL "RIDS" RECIPIENIS'LEASE HELP US K) REMJCE WASTEl CXNZACZ 'lHE DOCUMEPZ COÃI$OL DESK ROOM Pl-37 (EXT. 20079) KO XLIMZLTE YOUR NAME FMM DICTION LISTS POR DOCUMEMIS YOU DCINIT NEZDf TOTAL NUMBER OF COPXES REQUIRED: LTTR                       28   ENCL


==Dear Hr.Martin:==
~ .
I~ A
(..  ~
    .2  ~
WASHINGTON PUBLIC POWER SUPPLY Sly            SYSQRIVP M'lW 41
                                                                              ~ $
P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352
                                                              ~ I ARZ7    A  9: P3 Docket No. 50-39/
March 22, 1989 Nr. J.B. Martin Regional Administrator USNRC,    Region  V 1450 Maria Lane,    Suite 210 Walnut Creek,    CA  94596
 
==Dear Hr. Martin:==


==SUBJECT:==
==SUBJECT:==
NUCLEAR PLANT NO.2 LICENSE NO.NPF-21 SPECIAL REPORT'OST-ACCIDENT SANPLING PRIHARY COOLANT RADIATION NONITOR  
NUCLEAR PLANT NO. 2 LICENSE NO. NPF-21 SPECIAL REPORT'OST-ACCIDENT SANPLING PRIHARY COOLANT RADIATION NONITOR


==REFERENCE:==
==REFERENCE:==
Letter,  GC Sorensen  (SS) to JB Hartin (NRC), "Special Report:
Post-Accident Sampling Containment Atmosphere Radiation Monitor,"
Dated February 16, 1989 This special report is submitted pursuant to the requirements of WNP-2 Technical Specification Table 3.3.7.5-1 (Instrument No. 29: Post Accident Sampling Primary Coolant Radiation Monitor), Action Statement 81.
Action Statement 81 requires, "with the number of operable accident monitoring instrumentation channels less than required by the minimum channels operable requirement, either restore the inoperable channel(s) to operable status within 72 hours, or:
(a)    Initiate  the preplanned alternate method of monitoring the appropriate parameter(s), and (b)    In lieu of any other report required by Specification 6.9.1 prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule For restoring the system to operable status."
8904050343 890322 PDR S
ADOCK 05000397 PDC
                                                                                    'yp/
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PASS REPORT PAGE 2 In the referenced  letter, the Supply System reported that Post Accident Samp-ling  System (PASS) vacuum pump PSR-P-702 (Suppression Pool Atmospheric Sample Return) was inoperable and, as a result, Post Accident Sampling Containment Atmospheric Radiation Monitor PSR-RI-704 was unable to perform its function as required by the Technical Specifications. Also in the letter, the Supply System provided the plans and schedule For restoring the system to operable status and committed    to provide an evaluation of the failure  mode  of the vacuum pump.
On  March 6, 1989 as part of the repair efforts associated with PSR-P-702,    it was  necessary to remove the entire PASS from service and, as a result, the other Technical Specification instrument in the system (PSR-RI-665: Post Accident Sampling Primary Coolant Radiation Nonitor) was also not able to perform its required function.
In the event of an inoperable PASS during accident conditions, the alternate preplanned method for assessing core damage is Plant Procedure ( PPN) 9.3.22, "Core Damage Evaluation." Included in this procedure are evaluations of water level history, installed radiation monitor indication and hydrogen content in the containment atmosphere.
During the disassembly of PSR-P-702, water was discovered in the pump above the reed valve, which prevented the pump from establishing a vacuum (subsequent bench testing revealed that there were no mechanical problems with the pump). The PASS procedure requires purging Following pump operation to remove any moisture From the sample piping. However, due to a loose bulkhead fitting inside Sample Rack PSR-SR-06, there was insufficient flow available in the nitrogen purge supply line to adequately purge the water in the line.
Therefore, the excess moisture had 'settled in the pump.
Regarding restoring the system to operable status, PSR-P-702 was replaced with a new pump and  the bulkhead fitting repai'red. Current plans are to have the system aligned, tested and returned to service by Narch 31, 1989.
Very  truly yours, gal' C.M. Powers  (M/D 927M)
WNP-2  Plant Manager cc:  Mr. C.J. Bosted, NRC Site (N/0 901A)
Ns. Dottie Sherman, ANI Nr. D.L. Williams, BPA (N/D 399)
Document Control Desk, NRC


Letter, GC Sorensen (SS)to JB Hartin (NRC),"Special Report: Post-Accident Sampling Containment Atmosphere Radiation Monitor," Dated February 16, 1989 This special report is submitted pursuant to the requirements of WNP-2 Technical Specification Table 3.3.7.5-1 (Instrument No.29: Post Accident Sampling Primary Coolant Radiation Monitor), Action Statement 81.Action Statement 81 requires,"with the number of operable accident monitoring instrumentation channels less than required by the minimum channels operable requirement, either restore the inoperable channel(s) to operable status within 72 hours, or: (a)Initiate the preplanned alternate method of monitoring the appropriate parameter(s), and (b)In lieu of any other report required by Specification 6.9.1 prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule For restoring the system to operable status." 8904050343 890322 PDR ADOCK 05000397 S PDC'yp/
e' ill}}
0 r~y~~~y~1 w (,'I'll Jfi II ,t 1 PASS REPORT PAGE 2 In the referenced letter, the Supply System reported that Post Accident Samp-ling System (PASS)vacuum pump PSR-P-702 (Suppression Pool Atmospheric Sample Return)was inoperable and, as a result, Post Accident Sampling Containment Atmospheric Radiation Monitor PSR-RI-704 was unable to perform its function as required by the Technical Specifications.
Also in the letter, the Supply System provided the plans and schedule For restoring the system to operable status and committed to provide an evaluation of the failure mode of the vacuum pump.On March 6, 1989 as part of the repair efforts associated with PSR-P-702, it was necessary to remove the entire PASS from service and, as a result, the other Technical Specification instrument in the system (PSR-RI-665:
Post Accident Sampling Primary Coolant Radiation Nonitor)was also not able to perform its required function.In the event of an inoperable PASS during accident conditions, the alternate preplanned method for assessing core damage is Plant Procedure (PPN)9.3.22,"Core Damage Evaluation." Included in this procedure are evaluations of water level history, installed radiation monitor indication and hydrogen content in the containment atmosphere.
During the disassembly of PSR-P-702, water was discovered in the pump above the reed valve, which prevented the pump from establishing a vacuum (subsequent bench testing revealed that there were no mechanical problems with the pump).The PASS procedure requires purging Following pump operation to remove any moisture From the sample piping.However, due to a loose bulkhead fitting inside Sample Rack PSR-SR-06, there was insufficient flow available in the nitrogen purge supply line to adequately purge the water in the line.Therefore, the excess moisture had'settled in the pump.Regarding restoring the system to operable status, PSR-P-702 was replaced with a new pump and the bulkhead fitting repai'red.
Current plans are to have the system aligned, tested and returned to service by Narch 31, 1989.Very truly yours, gal'C.M.Powers (M/D 927M)WNP-2 Plant Manager cc: Mr.C.J.Bosted, NRC Site (N/0 901A)Ns.Dottie Sherman, ANI Nr.D.L.Williams, BPA (N/D 399)Document Control Desk, NRC ill e'}}

Latest revision as of 13:39, 29 October 2019

Special Rept:On 890306,post-accident Sampling Primary Coolant Radiation Monitor Inoperable.Caused by Excess Moisture.Pass Vacuum Pump PSR-P-702 Replaced W/New Pump & Bulkhead Fitting Repaired
ML17285A351
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 03/22/1989
From: Powers C
WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To: Martin J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
NUDOCS 8904050343
Download: ML17285A351 (6)
v • d • e


Text

p 4C CELE RATED D1FJBUT1 ON DE M ON STR+ON SYSTEM i'EGULATORY XNFORMATION DISTRXBUTION SYSTEM (RIDS)

ACCESSION NBR:8904050343 DOC.DATE: 89/03/22 NOTARIZED: NO DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION POWERS,C.M. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION MARTIN,J.B. Region 5, Ofc of the Director

SUBJECT:

Special rept:on 890306,post-accident sampling primary coolant radiation monitor inoperable.

DISTRIBUTION CODE: AOOID TITLE: OR Submittal: General Distribution COPIES RECEIVED:LTR j ENCL + SIZE:

NOTES:

RECIPIENT COPIES COPXES ID PD5 LA CODE/NAME SAMWORTH,R 1'ECIPIENT LTTR ENCL 1

5 '

ID PD5 PD CODE/NAME LTTR ENCL INTERNAL: ACRS ARM/DAF/LFMB NRR/DEST/ADS 7E 1 NRR/DEST/CEB 8H NRR/DEST/ESB 8D 1 NRR/DEST/ICSB NRR/DEST/MTB 9H 1 NRR/DEST/RSB 8E NRR/DOEA/TSB 11 1 J)OC~BSTRA~

OGC/HDS2 1 EG FILE 01 RES/DS XR/EIB EXTERNAL: LPDR NRC PDR NSIC NOTE TO ALL "RIDS" RECIPIENIS'LEASE HELP US K) REMJCE WASTEl CXNZACZ 'lHE DOCUMEPZ COÃI$OL DESK ROOM Pl-37 (EXT. 20079) KO XLIMZLTE YOUR NAME FMM DICTION LISTS POR DOCUMEMIS YOU DCINIT NEZDf TOTAL NUMBER OF COPXES REQUIRED: LTTR 28 ENCL

~ .

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(.. ~

.2 ~

WASHINGTON PUBLIC POWER SUPPLY Sly SYSQRIVP M'lW 41

~ $

P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352

~ I ARZ7 A 9: P3 Docket No. 50-39/

March 22, 1989 Nr. J.B. Martin Regional Administrator USNRC, Region V 1450 Maria Lane, Suite 210 Walnut Creek, CA 94596

Dear Hr. Martin:

SUBJECT:

NUCLEAR PLANT NO. 2 LICENSE NO. NPF-21 SPECIAL REPORT'OST-ACCIDENT SANPLING PRIHARY COOLANT RADIATION NONITOR

REFERENCE:

Letter, GC Sorensen (SS) to JB Hartin (NRC), "Special Report:

Post-Accident Sampling Containment Atmosphere Radiation Monitor,"

Dated February 16, 1989 This special report is submitted pursuant to the requirements of WNP-2 Technical Specification Table 3.3.7.5-1 (Instrument No. 29: Post Accident Sampling Primary Coolant Radiation Monitor), Action Statement 81.

Action Statement 81 requires, "with the number of operable accident monitoring instrumentation channels less than required by the minimum channels operable requirement, either restore the inoperable channel(s) to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or:

(a) Initiate the preplanned alternate method of monitoring the appropriate parameter(s), and (b) In lieu of any other report required by Specification 6.9.1 prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule For restoring the system to operable status."

8904050343 890322 PDR S

ADOCK 05000397 PDC

'yp/

0 r ~ y

~

~ ~y~ 1 II w

(,'I 'll Jfi ,t 1

PASS REPORT PAGE 2 In the referenced letter, the Supply System reported that Post Accident Samp-ling System (PASS) vacuum pump PSR-P-702 (Suppression Pool Atmospheric Sample Return) was inoperable and, as a result, Post Accident Sampling Containment Atmospheric Radiation Monitor PSR-RI-704 was unable to perform its function as required by the Technical Specifications. Also in the letter, the Supply System provided the plans and schedule For restoring the system to operable status and committed to provide an evaluation of the failure mode of the vacuum pump.

On March 6, 1989 as part of the repair efforts associated with PSR-P-702, it was necessary to remove the entire PASS from service and, as a result, the other Technical Specification instrument in the system (PSR-RI-665: Post Accident Sampling Primary Coolant Radiation Nonitor) was also not able to perform its required function.

In the event of an inoperable PASS during accident conditions, the alternate preplanned method for assessing core damage is Plant Procedure ( PPN) 9.3.22, "Core Damage Evaluation." Included in this procedure are evaluations of water level history, installed radiation monitor indication and hydrogen content in the containment atmosphere.

During the disassembly of PSR-P-702, water was discovered in the pump above the reed valve, which prevented the pump from establishing a vacuum (subsequent bench testing revealed that there were no mechanical problems with the pump). The PASS procedure requires purging Following pump operation to remove any moisture From the sample piping. However, due to a loose bulkhead fitting inside Sample Rack PSR-SR-06, there was insufficient flow available in the nitrogen purge supply line to adequately purge the water in the line.

Therefore, the excess moisture had 'settled in the pump.

Regarding restoring the system to operable status, PSR-P-702 was replaced with a new pump and the bulkhead fitting repai'red. Current plans are to have the system aligned, tested and returned to service by Narch 31, 1989.

Very truly yours, gal' C.M. Powers (M/D 927M)

WNP-2 Plant Manager cc: Mr. C.J. Bosted, NRC Site (N/0 901A)

Ns. Dottie Sherman, ANI Nr. D.L. Williams, BPA (N/D 399)

Document Control Desk, NRC

e' ill

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