NRC Generic Letter 1980-04: Difference between revisions

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{{#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:
{{#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
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:
414 Nicollet Mall Minneapolis, MN     55401 Gentlemen:
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
Enclosed is IE Bulletin No. 80-01 which requires action by you with regard to your BWR power reactor facility with an operating license.
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.
Should you have questions regarding this Bulletin or the actions required of you, please contact this office.


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.
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


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.
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.


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.
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.


6. Provide a response in writing by January 18, 1980, for those facilities which use a pneumatic operator for ADS function.Reports should be and a copy should of Inspection and Washington, D.C.submitted to the Director of the appropriate NRC Regional Office be forwarded to the U.S. Nuclear Regulatory Commission, Office Enforcement, Division of Reactor Operations Inspection, 20555.Approved by GAO, B180225 (R0072); clearance expires July 31, 1980.given under a blanket clearance specifically for identified generic Approval was problems.Attachment:
Actions to be taken by Licensees of GE BWR facilities with an operating license which use a pneumatic operator for ADS function:
Sketch of ADS pneumatic supply IE Bulletin January 11, No. 80-01 1980 Enclosure RECENTLY ISSUED IE BULLETINS Bulletin No.79-O1B Subject Environmental Qualification of Class IE Equipment Date Issued 1/14/80 Issued To All power reactor facilities with an OL 79-28 79-27 79-26 79-25 Possible Malfunction of Namco Model EA 180 Limit Switches at Elevated Temperatures Loss Of Non-Class-1-E
1.  Determine if your facility has installed hard-seat check valves to isolate the ADS accumlator system from the pneumatic supply system.
Instrumentation and Control Power System Bus During Operation Boron Loss From BWR Control Blades Failures of Westinghouse BFD Relays In Safety-Related Systems Pipe Cracks In Stagnant Borated Water System At PWR Plants Frozen Lines Potential Failure of Emergency Diesel Generator Field Exciter Transformer
 
12/7/79 11/30/79 11/20/79 11/2/79 10/29/79 9/27/79 9/12/79 All power reactor facilities with an OL or a CP All power reactor facilities holding OLs and to those nearing licensing All BWR power reactor facilities with an OL All power reactor facilities with an OL or CP All PWR's with an OL and for information to other power reactors All power reactor facilities which have either OLs or CPs and are in the late stage of construction All Power Reactor Facilities with an Operating License or a construction permit 79-17 (Rev. 1)79-24 79-23 79-14 (Supplement
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.
2)Seismic Analyses For As-Built Safety-Related Piping Systems 9/7/79 All Power Reactor Facilities with an OL or a CP  
 
i A A Fm a -- --ADS Valve N DryweLL WaLL VI A< ,t f>A- _ _ wo-l~}}
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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