NRC Generic Letter 1980-04: Difference between revisions

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| issue date = 01/11/1980
| issue date = 01/11/1980
| title = NRC Generic Letter 1980-004, Transmittal of IE Bulletin 1980-001: Operability of ADS Valve Pneumatic Supply
| title = NRC Generic Letter 1980-004, Transmittal of IE Bulletin 1980-001: Operability of ADS Valve Pneumatic Supply
| author name = Keppler J G
| author name = Keppler J
| author affiliation = NRC/NRR
| author affiliation = NRC/NRR
| addressee name =  
| addressee name =  
Line 15: Line 15:
| page count = 5
| page count = 5
}}
}}
{{#Wiki_filter:G-go fDocket No. 50-263 1AN11 E8cNorthern States Power CompanyATTN: Mr. Dennis E. GilbertsVice PresidentPower Production andSystem Operation414 Nicollet MallMinneapolis, MN 55401Gentlemen:Enclosed is IE Bulletin No. 80-01 which requires action by you with regardto your BWR power reactor facility with an operating license.Should you have questions regarding this Bulletin or the actions requiredof you, please contact this office.Sincerely,James G. KepplerDirectorEnclosure: IE BulletinNo. 80-01cc w/encl:Mr. L. R. Eliason,Plant ManagerCentral FilesDirector, NRR/DPMDirector, NRR/DORPDRLocal PDRNSICTICJohn W. Ferman, Ph.D.,Nuclear Engineer, HPCARI E RWHe s an/bk Keppler1/11/808 00 1280 504 UNITED STATES SSINS No.: 6870NUCLEAR REGULATORY COMMISSION Accessions No.:OFFICE OF INSPECTION AND ENFORCEMENT 7912190652WASHINGTON, D.C. 20555January 11, 1980IE Bulletin No. 80-01OPERABILITY OF ADS VALVE PNEUMATIC SUPPLYOn January 10, 1980, the NRC was informed by Philadelphia Electric Company thatengineering evaluation for Peach Bottom 2 and 3 has disclosed that the AutomaticDepressurization System (ADS) pneumatic supply (either nitrogen or air) may notbe operable for all possible events because of a combination of misapplicationof check valve, a lack of leak testing of the accumulator system backing up eachADS valve operator and questions about the continued operability of the pneumaticsupply in a seismic event. Attached is a simplified schematic of the pneumaticsupply. The check valve nearest to the accumulator is a PAL, three-quarter inch,stainless steel, socket welded check valve with a hard seat (valve identification-B-1376 on the upper flange). Plant information at Peach Bottom shows substantialsupports for the pneumatic supply inside the drywell, but seismic qualificationhas not been verified. The licensee has stated that the pneumatic supply is notseismically qualified outside the drywell.Unit 2 was shutdown on 1/10/80 because of questions of ADS operability and Unit 3has been provided a seismically qualified nitrogen supply at the containmentpenetration pending confirmation of seismic qualification of piping inside Unit 2containment. The licensee is changing their valve to one with a soft seat toreduce leakage.Actions to be taken by Licensees of GE BWR facilities with an operating licensewhich use a pneumatic operator for ADS function:1. Determine if your facility has installed hard-seat check valves to isolatethe ADS accumlator system from the pneumatic supply system.2. Determine if periodic leak tests have been performed on your ADS accumulatorsystems to assure emergency pneumatic supply for the FSAR-required numberand duration of valve operations.3. Review seismic qualifications of the ADS pneumatic supply system:(a) from accumulator system isolation check valve to ADS valve operator,(b) from isolation valve outside containment up to ADS accumulator checkvalve.4. Based upon determination of items 1, 2 and 3 above, evaluate operabilityof the ADS for the conditions under which it is required to be operableincluding a seismic event. If operability cannot be established adhereto appropriate Technical Specification action statement.
{{#Wiki_filter:G-go f Docket No. 50-263                                         1AN11 E8c Northern States Power Company ATTN: Mr. Dennis E. Gilberts Vice President Power Production and System Operation
414 Nicollet Mall Minneapolis, MN     55401 Gentlemen:
Enclosed is IE Bulletin No. 80-01 which requires action by you with regard to your BWR power reactor facility with an operating license.


IE Bulletin No. 80-01 January 11, 1980 . Provide an immediate notification to the NRC in the event the ADS is foundto be inoperable.6. Provide a response in writing by January 18, 1980, for those facilitieswhich use a pneumatic operator for ADS function.Reports should beand a copy shouldof Inspection andWashington, D.C.submitted to the Director of the appropriate NRC Regional Officebe forwarded to the U.S. Nuclear Regulatory Commission, OfficeEnforcement, Division of Reactor Operations Inspection,20555.Approved by GAO, B180225 (R0072); clearance expires July 31, 1980.given under a blanket clearance specifically for identified genericApproval wasproblems.Attachment:Sketch of ADS pneumatic supply IE BulletinJanuary 11,No. 80-011980EnclosureRECENTLY ISSUEDIE BULLETINSBulletinNo.79-O1BSubjectEnvironmental Qualificationof Class IE EquipmentDate Issued1/14/80Issued ToAll power reactorfacilities with anOL79-2879-2779-2679-25Possible Malfunction ofNamco Model EA 180 LimitSwitches at ElevatedTemperaturesLoss Of Non-Class-1-EInstrumentation andControl Power System BusDuring OperationBoron Loss From BWRControl BladesFailures of WestinghouseBFD Relays In Safety-RelatedSystemsPipe Cracks In StagnantBorated Water System AtPWR PlantsFrozen LinesPotential Failure ofEmergency DieselGenerator FieldExciter Transformer12/7/7911/30/7911/20/7911/2/7910/29/799/27/799/12/79All power reactorfacilities with anOL or a CPAll power reactorfacilities holdingOLs and to thosenearing licensingAll BWR power reactorfacilities with anOLAll power reactorfacilities with anOL or CPAll PWR's with anOL and for informationto other power reactorsAll power reactorfacilities which haveeither OLs or CPs andare in the late stageof constructionAll Power ReactorFacilities with anOperating License ora construction permit79-17(Rev. 1)79-2479-2379-14(Supplement 2)Seismic Analyses ForAs-Built Safety-RelatedPiping Systems9/7/79All Power ReactorFacilities with anOL or a CP  
Should you have questions regarding this Bulletin or the actions required of you, please contact this office.
i AA Fm a -- --ADS ValveNDryweLL WaLLVIA< ,tf>A- _ _ wo-l~  
 
}}
Sincerely, James G. Keppler Director Enclosure: IE Bulletin No. 80-01 cc w/encl:
Mr. L. R. Eliason, Plant Manager Central Files Director, NRR/DPM
Director, NRR/DOR
PDR
Local PDR
NSIC
TIC
John W. Ferman, Ph.D.,
  Nuclear Engineer, HPCA
RI E            RW
He s an/bk      Keppler
1/11/80
                                                          8 00 1280 504
 
UNITED STATES                  SSINS No.: 6870
                          NUCLEAR REGULATORY COMMISSION          Accessions No.:
                      OFFICE OF INSPECTION AND ENFORCEMENT      7912190652 WASHINGTON, D.C. 20555 January 11, 1980
                                                            IE Bulletin No. 80-01 OPERABILITY OF ADS VALVE PNEUMATIC SUPPLY
On January 10, 1980, the NRC was informed by Philadelphia Electric Company that engineering evaluation for Peach Bottom 2 and 3 has disclosed that the Automatic Depressurization System (ADS) pneumatic supply (either nitrogen or air) may not be operable for all possible events because of a combination of misapplication of check valve, a lack of leak testing of the accumulator system backing up each ADS valve operator and questions about the continued operability of the pneumatic supply in a seismic event. Attached is a simplified schematic of the pneumatic supply. The check valve nearest to the accumulator is a PAL, three-quarter inch, stainless steel, socket welded check valve with a hard seat (valve identification- B-1376 on the upper flange). Plant information at Peach Bottom shows substantial supports for the pneumatic supply inside the drywell, but seismic qualification has not been verified. The licensee has stated that the pneumatic supply is not seismically qualified outside the drywell.
 
Unit 2 was shutdown on 1/10/80 because of questions of ADS operability and Unit 3 has been provided a seismically qualified nitrogen supply at the containment penetration pending confirmation of seismic qualification of piping inside Unit 2 containment. The licensee is changing their valve to one with a soft seat to reduce leakage.
 
Actions to be taken by Licensees of GE BWR facilities with an operating license which use a pneumatic operator for ADS function:
1.  Determine if your facility has installed hard-seat check valves to isolate the ADS accumlator system from the pneumatic supply system.
 
2.  Determine if periodic leak tests have been performed on your ADS accumulator systems to assure emergency pneumatic supply for the FSAR-required number and duration of valve operations.
 
3.  Review seismic qualifications of the ADS pneumatic supply system:
    (a) from accumulator system isolation check valve to ADS valve operator, (b) from isolation valve outside containment up to ADS accumulator check valve.
 
4.  Based upon determination of items 1, 2 and 3 above, evaluate operability of the ADS for the conditions under which it is required to be operable including a seismic event. If operability cannot be established adhere to appropriate Technical Specification action statement.
 
IE Bulletin No. 80-01                                           January 11, 1980 5.   Provide an immediate notification to the NRC in the event the ADS is found to be inoperable.
 
6.   Provide a response in writing by January 18, 1980, for those facilities which use a pneumatic operator for ADS function.
 
Reports should be submitted to the Director of the appropriate NRC Regional Office and a copy should be forwarded to the U.S. Nuclear Regulatory Commission, Office of Inspection and Enforcement, Division of Reactor Operations Inspection, Washington, D.C.  20555.
 
Approved by GAO, B180225 (R0072); clearance expires July 31, 1980. Approval was given under a blanket clearance specifically for identified generic problems.
 
Attachment:
Sketch of ADS pneumatic supply
 
IE Bulletin No. 80-01                                            Enclosure January 11, 1980
                                  RECENTLY ISSUED
                                    IE BULLETINS
Bulletin        Subject                      Date Issued  Issued To No.
 
79-O1B          Environmental Qualification  1/14/80    All power reactor of Class IE Equipment                      facilities with an OL
79-28          Possible Malfunction of      12/7/79    All power reactor Namco Model EA 180 Limit                  facilities with an Switches at Elevated                      OL or a CP
                Temperatures
79-27          Loss Of Non-Class-1-E        11/30/79    All power reactor Instrumentation and                      facilities holding Control Power System Bus                  OLs and to those During Operation                          nearing licensing
79-26          Boron Loss From BWR          11/20/79    All BWR power reactor Control Blades                            facilities with an OL
79-25          Failures of Westinghouse      11/2/79    All power reactor BFD Relays In Safety-Related              facilities with an Systems                                  OL or CP
79-17          Pipe Cracks In Stagnant      10/29/79    All PWR's with an (Rev. 1)        Borated Water System At                  OL and for information PWR Plants                                to other power reactors
79-24          Frozen Lines                  9/27/79    All power reactor facilities which have either OLs or CPs and are in the late stage of construction
79-23          Potential Failure of          9/12/79    All Power Reactor Emergency Diesel                          Facilities with an Generator Field                          Operating License or Exciter Transformer                      a construction permit
79-14           Seismic Analyses For          9/7/79    All Power Reactor (Supplement 2) As-Built Safety-Related                    Facilities with an Piping Systems                            OL or a CP
 
iA
                          a --   - -
                      A Fm ADS Valve N
        DryweLL WaLL
  A< ,t VI                                        _ wo-l~}}


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Latest revision as of 01:53, 24 November 2019

NRC Generic Letter 1980-004, Transmittal of IE Bulletin 1980-001: Operability of ADS Valve Pneumatic Supply
ML031350303
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 01/11/1980
From: James Keppler
Office of Nuclear Reactor Regulation
To:
References
BL-80-001 GL-80-004, NUDOCS 8001280504
Download: ML031350303 (5)


G-go f Docket No. 50-263 1AN11 E8c Northern States Power Company ATTN: Mr. Dennis E. Gilberts Vice President Power Production and System Operation

414 Nicollet Mall Minneapolis, MN 55401 Gentlemen:

Enclosed is IE Bulletin No. 80-01 which requires action by you with regard to your BWR power reactor facility with an operating license.

Should you have questions regarding this Bulletin or the actions required of you, please contact this office.

Sincerely, James G. Keppler Director Enclosure: IE Bulletin No. 80-01 cc w/encl:

Mr. L. R. Eliason, Plant Manager Central Files Director, NRR/DPM

Director, NRR/DOR

PDR

Local PDR

NSIC

TIC

John W. Ferman, Ph.D.,

Nuclear Engineer, HPCA

RI E RW

He s an/bk Keppler

1/11/80

8 00 1280 504

UNITED STATES SSINS No.: 6870

NUCLEAR REGULATORY COMMISSION Accessions No.:

OFFICE OF INSPECTION AND ENFORCEMENT 7912190652 WASHINGTON, D.C. 20555 January 11, 1980

IE Bulletin No. 80-01 OPERABILITY OF ADS VALVE PNEUMATIC SUPPLY

On January 10, 1980, the NRC was informed by Philadelphia Electric Company that engineering evaluation for Peach Bottom 2 and 3 has disclosed that the Automatic Depressurization System (ADS) pneumatic supply (either nitrogen or air) may not be operable for all possible events because of a combination of misapplication of check valve, a lack of leak testing of the accumulator system backing up each ADS valve operator and questions about the continued operability of the pneumatic supply in a seismic event. Attached is a simplified schematic of the pneumatic supply. The check valve nearest to the accumulator is a PAL, three-quarter inch, stainless steel, socket welded check valve with a hard seat (valve identification- B-1376 on the upper flange). Plant information at Peach Bottom shows substantial supports for the pneumatic supply inside the drywell, but seismic qualification has not been verified. The licensee has stated that the pneumatic supply is not seismically qualified outside the drywell.

Unit 2 was shutdown on 1/10/80 because of questions of ADS operability and Unit 3 has been provided a seismically qualified nitrogen supply at the containment penetration pending confirmation of seismic qualification of piping inside Unit 2 containment. The licensee is changing their valve to one with a soft seat to reduce leakage.

Actions to be taken by Licensees of GE BWR facilities with an operating license which use a pneumatic operator for ADS function:

1. Determine if your facility has installed hard-seat check valves to isolate the ADS accumlator system from the pneumatic supply system.

2. Determine if periodic leak tests have been performed on your ADS accumulator systems to assure emergency pneumatic supply for the FSAR-required number and duration of valve operations.

3. Review seismic qualifications of the ADS pneumatic supply system:

(a) from accumulator system isolation check valve to ADS valve operator, (b) from isolation valve outside containment up to ADS accumulator check valve.

4. Based upon determination of items 1, 2 and 3 above, evaluate operability of the ADS for the conditions under which it is required to be operable including a seismic event. If operability cannot be established adhere to appropriate Technical Specification action statement.

IE Bulletin No. 80-01 January 11, 1980 5. Provide an immediate notification to the NRC in the event the ADS is found to be inoperable.

6. Provide a response in writing by January 18, 1980, for those facilities which use a pneumatic operator for ADS function.

Reports should be submitted to the Director of the appropriate NRC Regional Office and a copy should be forwarded to the U.S. Nuclear Regulatory Commission, Office of Inspection and Enforcement, Division of Reactor Operations Inspection, Washington, D.C. 20555.

Approved by GAO, B180225 (R0072); clearance expires July 31, 1980. Approval was given under a blanket clearance specifically for identified generic problems.

Attachment:

Sketch of ADS pneumatic supply

IE Bulletin No. 80-01 Enclosure January 11, 1980

RECENTLY ISSUED

IE BULLETINS

Bulletin Subject Date Issued Issued To No.

79-O1B Environmental Qualification 1/14/80 All power reactor of Class IE Equipment facilities with an OL

79-28 Possible Malfunction of 12/7/79 All power reactor Namco Model EA 180 Limit facilities with an Switches at Elevated OL or a CP

Temperatures

79-27 Loss Of Non-Class-1-E 11/30/79 All power reactor Instrumentation and facilities holding Control Power System Bus OLs and to those During Operation nearing licensing

79-26 Boron Loss From BWR 11/20/79 All BWR power reactor Control Blades facilities with an OL

79-25 Failures of Westinghouse 11/2/79 All power reactor BFD Relays In Safety-Related facilities with an Systems OL or CP

79-17 Pipe Cracks In Stagnant 10/29/79 All PWR's with an (Rev. 1) Borated Water System At OL and for information PWR Plants to other power reactors

79-24 Frozen Lines 9/27/79 All power reactor facilities which have either OLs or CPs and are in the late stage of construction

79-23 Potential Failure of 9/12/79 All Power Reactor Emergency Diesel Facilities with an Generator Field Operating License or Exciter Transformer a construction permit

79-14 Seismic Analyses For 9/7/79 All Power Reactor (Supplement 2) As-Built Safety-Related Facilities with an Piping Systems OL or a CP

iA

a -- - -

A Fm ADS Valve N

DryweLL WaLL

A< ,t VI _ wo-l~

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