NRC Generic Letter 1990-03: Difference between revisions

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| issue date = 03/20/1990
| issue date = 03/20/1990
| title = NRC Generic Letter 1990-003: Relaxation of Staff Position in Generic Letter 83-28, Item 2.2 Part 2 Vendor Interface for Safety-Related Components
| title = NRC Generic Letter 1990-003: Relaxation of Staff Position in Generic Letter 83-28, Item 2.2 Part 2 Vendor Interface for Safety-Related Components
| author name = Partlow J G
| author name = Partlow J
| author affiliation = NRC/NRR
| author affiliation = NRC/NRR
| addressee name =  
| addressee name =  
Line 15: Line 15:
| page count = 6
| page count = 6
}}
}}
{{#Wiki_filter:; ^s-UNITED STATES NUCLEAR REGULATORY  
{{#Wiki_filter:; ^s- UNITED STATES
COMMISSION
                              NUCLEAR REGULATORY COMMISSION
WASHINGTON, D. C. 20555 March 20, 1990 TO: ALL POWER REACTOR LICENSEES  
                                      WASHINGTON, D. C. 20555 March 20, 1990
AND APPLICANTS
      TO:       ALL POWER REACTOR LICENSEES AND APPLICANTS
SUBJECT: RELAXATION  
      SUBJECT:   RELAXATION OF STAFF POSITION IN GENERIC LETTER 83-28, ITEM 2.2 PART 2 "VENDOR INTERFACE FOR SAFETY-RELATED COMPONENTS"
OF STAFF POSITION IN GENERIC LETTER 83-28, ITEM 2.2 PART 2 "VENDOR INTERFACE  
                  (GENERIC LETTER NO. 90-03)
FOR SAFETY-RELATED  
      This letter is to clarify the staff position in Part 2 of Item 2.2 of Generic Letter 83-28 (Vendor Interface for Safety-Related Components).
COMPONENTS" (GENERIC LETTER NO. 90-03)This letter is to clarify the staff position in Part 2 of Item 2.2 of Generic Letter 83-28 (Vendor Interface for Safety-Related Components).
      The original position reads as follows:
The original position reads as follows: "For vendor interface, licensees and applicants shall establish, implement and maintain a continuing program to ensure that vendor information for safety-related components is complete, current and controlled throughout the life of their plants, and is appropriately referenced or incorporated in plant instructions and procedures.
            "For vendor interface, licensees and applicants shall establish, implement and maintain a continuing program to ensure that vendor information for safety-related components is complete, current and controlled throughout the life of their plants, and is appropriately referenced or incorporated in plant instructions and procedures. Vendors of safety-related equipment should be contacted and an interface established. Where vendors cannot be identified, have gone out of business, or will not supply information, the licensee or applicant shall assure that sufficient attention is paid to equipment maintenance, replacement, and repair, to compensate for the lack of vendor backup, to assure reliability commensurate with its safety function (GDC-1). The program shall be closely coupled with action 2.2.1 (equipment classification). The program shall include periodic communication with vendors to assure that all applicable information has been received.


Vendors of safety-related equipment should be contacted and an interface established.
The program should use a system of positive feedback with vendors for mailings containing technical information. This could be accomplished by licensee acknowledgement for receipt of technical mailings. It shall also define the interface and division of responsibilities among the licensee and the nuclear and non-nuclear divisions of their vendors that provide service on safety-related equipment to assure that requisite control of and applicable instructions for maintenance work on safety-related equipment are provided."
      Since this position was established, the industry has generally taken the position that the Vendor Equipment Technical Information Program (VETIP)
      described in the Nuclear Utility Task Action Committee (NUTAC) Report, INPO
      84-010 issued in March 1984, meets the intent of Generic Letter 83-28, Item 2.2 Part 2.- The VETIP program includes the Nuclear Plant Reliability Data System (NPRDS) and the Significant Event Evaluation and Information Network (SEE-IN), both managed by INPO. It also includes existing programs the utilities now conduct with vendors. In particular, it includes interaction with the NSSS vendor.


Where vendors cannot be identified, have gone out of business, or will not supply information, the licensee or applicant shall assure that sufficient attention is paid to equipment maintenance, replacement, and repair, to compensate for the lack of vendor backup, to assure reliability commensurate with its safety function (GDC-1). The program shall be closely coupled with action 2.2.1 (equipment classification).
90031 40089
The program shall include periodic communication with vendors to assure that all applicable information has been received.The program should use a system of positive feedback with vendors for mailings containing technical information.


This could be accomplished by licensee acknowledgement for receipt of technical mailings.
- 2 -
The staff has reviewed the VETIP program and has had the benefit of considerable discussions with licensees regarding vendor interface. It is now recognized that implementing a formal vendor interface program for every safety-related component is not practical. It is also recognized that vendors may not always be in the best position to analyze a failure because they may not be aware of the components' application, environment or maintenance history. Therefore, we conclude that the elements of VETIP
provide a framework to improve the quality and availability of equipment technical information for use by utility licensees.


It shall also define the interface and division of responsibilities among the licensee and the nuclear and non-nuclear divisions of their vendors that provide service on safety-related equipment to assure that requisite control of and applicable instructions for maintenance work on safety-related equipment are provided." Since this position was established, the industry has generally taken the position that the Vendor Equipment Technical Information Program (VETIP)described in the Nuclear Utility Task Action Committee (NUTAC) Report, INPO 84-010 issued in March 1984, meets the intent of Generic Letter 83-28, Item 2.2 Part 2.- The VETIP program includes the Nuclear Plant Reliability Data System (NPRDS) and the Significant Event Evaluation and Information Network (SEE-IN), both managed by INPO. It also includes existing programs the utilities now conduct with vendors. In particular, it includes interaction with the NSSS vendor.90031 40089
Experience has shown that many vendors, in addition to NSSS vendors, do produce valuable information relating to their equipment. For this reason, the staff concludes that an adequate vendor interface program should include:
-2 -The staff has reviewed the VETIP program and has had the benefit of considerable discussions with licensees regarding vendor interface.
      (a) A program with the NSSS vendor as described in the VETIP, which covers all the safety-related components within the NSSS scope of supply. This program should include provisions for assuring receipt by the licensee/applicant of all technical information provided by the NSSS vendor; and (b) A program of periodic contact with the vendors of other key safety-related components not included in (a) above.


It is now recognized that implementing a formal vendor interface program for every safety-related component is not practical.
The vendor interface program should also take into account the requirements of
10 CFR Part 50, Appendix B which requires the licensee or applicant to be responsible for establishing and executing the quality assurance program. It states that the licensee or applicant may delegate to others the work of establishing and executing the quality assurance program or any part of it, but the licensee or applicant shall retain responsibility for the program.


It is also recognized that vendors may not always be in the best position to analyze a failure because they may not be aware of the components'
Therefore, the licensee or applicant should have a program which assures that procedures and instructions are properly prepared and implemented and that quality assurance programs for design, maintenance or modification work performed on safety-related equipment by outside vendors or contractors are properly implemented. These programs should clearly establish and delineate in writing the authority and duties of persons and organizations performing activities affecting this safety-related equipment.
application, environment or maintenance history. Therefore, we conclude that the elements of VETIP provide a framework to improve the quality and availability of equipment technical information for use by utility licensees.


Experience has shown that many vendors, in addition to NSSS vendors, do produce valuable information relating to their equipment.
The programs in (a) above should provide for the licensee or applicant to receive all updates to instruction and maintenance manuals, technical information bulletins, revised test procedures, and updated replacement parts information. The programs should include provisions which ensure the licensee receives all such vendor issued information pertinent to its safety-related equipment.


For this reason, the staff concludes that an adequate vendor interface program should include: (a) A program with the NSSS vendor as described in the VETIP, which covers all the safety-related components within the NSSS scope of supply. This program should include provisions for assuring receipt by the licensee/applicant of all technical information provided by the NSSS vendor; and (b) A program of periodic contact with the vendors of other key safety-related components not included in (a) above.The vendor interface program should also take into account the requirements of 10 CFR Part 50, Appendix B which requires the licensee or applicant to be responsible for establishing and executing the quality assurance program. It states that the licensee or applicant may delegate to others the work of establishing and executing the quality assurance program or any part of it, but the licensee or applicant shall retain responsibility for the program.Therefore, the licensee or applicant should have a program which assures that procedures and instructions are properly prepared and implemented and that quality assurance programs for design, maintenance or modification work performed on safety-related equipment by outside vendors or contractors are properly implemented.
The program described in (b) above is not intended to be as extensive as the program in (a), but is intended to be a good faith, documented effort to periodically contact the vendors of key, safety-related components (such as auxiliary feedwater pumps, batteries, inverters, battery chargers, cooling water pumps and valve operators), not already included in the interface program of la) above, to obtain any technical information applicable to this


These programs should clearly establish and delineate in writing the authority and duties of persons and organizations performing activities affecting this safety-related equipment.
- 3 -
  equipment. Documented periodic contact via telephone is sufficient. It is expected that a reasonable and prudent review of operating experience, availability of vendor information, and component safety significance using insights obtained from generic or plant specific probabilistic risk analyses will yield a set of component vendors that will make up each licensee's program. In the event that vendors have gone out of business, cannot be identified, or will not supply information, the licensee or applicant should implement or continue to maintain a program that will assure that sufficient attention is paid to equipment maintenance, replacement, and repair to compensate for the lack of vendor backup such that equipment reliability commensurate with its safety function is assured.


The programs in (a) above should provide for the licensee or applicant to receive all updates to instruction and maintenance manuals, technical information bulletins, revised test procedures, and updated replacement parts information.
Licensees and applicants are requested to review their present vendor interface programs and modify their programs as necessary to assure that both of the elements set out above are met. Pursuant to Section 182 of the Atomic Energy Act and 10 CFR 50.54(f), the NRC requires that licensees report to the NRC
within 180 days of receipt of this generic letter whether or not they have taken the actions requested.


The programs should include provisions which ensure the licensee receives all such vendor issued information pertinent to its safety-related equipment.
Licensees undertaking the actions requested should confirm that they have examined their vendor interface programs, that their programs either already include both of the elements set out in this letter or that the elements have been scheduled for implementation. If licensee actions are not complete at the time of their submittal, the licensee should submit a completion date for the remaining actions to be taken. If the licensee declines to undertake the actions requested by this letter, the licensee is required to provide justifi- cation for the position.


The program described in (b) above is not intended to be as extensive as the program in (a), but is intended to be a good faith, documented effort to periodically contact the vendors of key, safety-related components (such as auxiliary feedwater pumps, batteries, inverters, battery chargers, cooling water pumps and valve operators), not already included in the interface program of la) above, to obtain any technical information applicable to this
The response to this letter is to be provided under oath or affirmation and is necessary to enable the Commission to determine whether or not your license should be modified, suspended, or revoked. The response shall be addressed to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D. C. 20555. The NRC will continue to monitor the effectiveness of licensee or applicant vendor interface program implementation through the inspection process and will use the responses to this letter to plan and locate resources for inspections. Where a licensee's failure to (1) obtain information from vendors, (2) evaluate information obtained from vendors, or
-3 -equipment.
(3) implement necessary actions based on information obtained from a vendor results in conditions adverse to quality, the NRC will make findings and take action in accordance with its regulations.


Documented periodic contact via telephone is sufficient.
This request is covered by the Office of Management and Budget Clearance Number
3150-0011, which expires January 31, 1991. The estimated average burden hours is 320 person hours per licensee response (144 person hours per year per licensee thereafter), including assessment of the new recommendations, searching data sources, gathering and analyzing the data, and preparing the required letters. Send comments regarding this burden estimate or any other aspect of this collection of information, including suggestions for reduting this burden, to the Records and Reports Management Branch, (MNBB-7714) Division of Information Support Services, Office of Information Resources Management, U.S. Nuclear Regulatory Commission, Washington, D. C. 20555; and to the Paperwork Reduction Project (3150-0011), Office of Management and Budget, Washington, D. C. 20503.


It is expected that a reasonable and prudent review of operating experience, availability of vendor information, and component safety significance using insights obtained from generic or plant specific probabilistic risk analyses will yield a set of component vendors that will make up each licensee's program. In the event that vendors have gone out of business, cannot be identified, or will not supply information, the licensee or applicant should implement or continue to maintain a program that will assure that sufficient attention is paid to equipment maintenance, replacement, and repair to compensate for the lack of vendor backup such that equipment reliability commensurate with its safety function is assured.Licensees and applicants are requested to review their present vendor interface programs and modify their programs as necessary to assure that both of the elements set out above are met. Pursuant to Section 182 of the Atomic Energy Act and 10 CFR 50.54(f), the NRC requires that licensees report to the NRC within 180 days of receipt of this generic letter whether or not they have taken the actions requested.
-4 -


Licensees undertaking the actions requested should confirm that they have examined their vendor interface programs, that their programs either already include both of the elements set out in this letter or that the elements have been scheduled for implementation.
==Backfit Discussion==
The actions described in this generic letter are relaxations of the original position taken in Generic Letter 83-28 and are not considered a backfit in accordance with NRC procedures. An evaluation of this letter was performed in accordance with the charter of the Committee to Review Generic Requirements (CRGR) and will be made available in the public document room with the minutes of the 178th meeting of the CRGR.


If licensee actions are not complete at the time of their submittal, the licensee should submit a completion date for the remaining actions to be taken. If the licensee declines to undertake the actions requested by this letter, the licensee is required to provide justifi-cation for the position.The response to this letter is to be provided under oath or affirmation and is necessary to enable the Commission to determine whether or not your license should be modified, suspended, or revoked. The response shall be addressed to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D. C. 20555. The NRC will continue to monitor the effectiveness of licensee or applicant vendor interface program implementation through the inspection process and will use the responses to this letter to plan and locate resources for inspections.
If you have any questions about this matter, please contact the NRC project manager or the technical contact listed below.


Where a licensee's failure to (1) obtain information from vendors, (2) evaluate information obtained from vendors, or (3) implement necessary actions based on information obtained from a vendor results in conditions adverse to quality, the NRC will make findings and take action in accordance with its regulations.
Sincerely, J4~7 sLJe James G. Partlow Associate Director for Projects Office of Nuclear Reactor Regulation Enclosure:
Listing of Recently Issued Generic Letters Technical Contacts:
S. Newberry, NRR
(301) 492-0782 D. LaBarge, NRR
(301) 492-1421


This request is covered by the Office of Management and Budget Clearance Number 3150-0011, which expires January 31, 1991. The estimated average burden hours is 320 person hours per licensee response (144 person hours per year per licensee thereafter), including assessment of the new recommendations, searching data sources, gathering and analyzing the data, and preparing the required letters. Send comments regarding this burden estimate or any other aspect of this collection of information, including suggestions for reduting this burden, to the Records and Reports Management Branch, (MNBB-7714)  
LIST OF RECENTLY ISSUED GENERIC LETTERS
Division of Information Support Services, Office of Information Resources Management, U.S. Nuclear Regulatory Commission, Washington, D. C. 20555; and to the Paperwork Reduction Project (3150-0011), Office of Management and Budget, Washington, D. C. 20503.
Generic                                      Date of A41                        TeVcanca      Issued To Letter No. e..k zUDJecL                              ---..--    ._____-._
          ALTERNATIVE REQUIREMENTS          02/01/90      ALL LWR LICENSEES
90-02 FOR FUEL ASSEMBLIES IN THE                        AND APPLICANTS
          DESIGN FEATURES SECTION OF
          TECHNICAL SPECIFICATIONS
90-01      REQUEST FOR VOLUNTARY            01/18/90      ALL LICENSEES OF
            PARTICIPATION IN NRC                            OPERATING REACTORS &
            REGULATORY IMPAC SURVEY                          CONSTRUCTION PERMITS
                                                              FOR LWR NUCLEAR POWER
                                                              PLANTS
89-23      NRC STAFF RESPONSES TO            10/23/89      ALL HOLDERS OF
            QUESTIONS PERTAINING TO                          OPERATING LICENSEES
            IMPLEMENTATION OF 10 CFR                        AND CONSTRUCTION
            PART 26 - GENERIC LETTER                        PERMITS FOR NUCLEAR
            89-23                                            POWER PLANTS
89-22      POTENTIAL FOR INCREASED ROOF      10/19/89      ALL LICENSEES OF
            LOADS AND PLANT AREA FLOOD                      OPERATING REACTORS AND
            RUNOFF DEPTH AT LICENSED                        HOLDERS OF CONSTRUCTION
            NUCLEAR POWER PLANTS DUE TO                      PERMITS (EXCEPT BYRON
            RECENT CHANGE IN PROBABLE                        BRAIDWOOD, VOGTLE,
            MAXIMUM PRECIPITATION                            SOUTH TEXAS, AND RIVER
            CRITERIA DEVELOPED BY THE                        BEND)
            NATIONAL WEATHER SERVICE
              (GENERIC LETTER 89-22)
89-21      REQUEST FOR INFORMATION          10/19/89      ALL HOLDERS OF
              CONCERNING STATUS OF                            OPERATING LICENSES
              IMPLEMENTATION OF UNRESOLVED                    AND CONSTRUCTION
              SAFETY ISSUE (USI) REQUIREMENTS                  PERMITS FOR NUCLEAR
                                                              POWER REACTORS
89-20        PROTECTED AREA LONG-TERM          09/26/89      ALL FUEL CYCLE
              HOUSEKEEPING                                    FACILITY LICENSEES
                                                              WHO POSSESS, USE,
                                                              OR PROCESS FORMULA
                                                              QUANTITIES OF
                                                              STRATEGIC SPECIAL
                                                              NUCLEAR MATERIAL
89-19        REQUEST FOR ACTION RELATED TO 09/20/89          ALL LICENSEES OF
              RESOLUTION OF UNRESOLVED                        OPERATING REACTORS,
              SAFETY ISSUE A-47 "SAFETY                      APPLICANTS FOR
                IMPLICATION OF CONTROL                        OPERATING LICENSES
              SYSTEMS IN LWR NUCLEAR                          AND HOLDERS OF
              POWER PLANTS" PURSUANT TO                      CONSTRUCTION PERMITS
                10 CFR 50.54(f)                                 FOR LIGHT WATER
                                                                REACTOR NUCLEAR
                                                                POWER PLANTS


-4 -
- 4 -


==Backfit Discussion==
==Backfit Discussion==
The actions described in this generic letter are relaxations of the original position taken in Generic Letter 83-28 and are not considered a backfit in accordance with NRC procedures.
The actions described in this generic letter are relaxations of the original position taken in Generic Letter 83-28 and are not considered a backfit in accordance with NRC procedures. An evaluation of this letter was performed in accordance with the charter of the Committee to Review Generic Requirements (CRGR) and will be made available in the public document room with the minutes of the 178th meeting of the CRGR.
 
An evaluation of this letter was performed in accordance with the charter of the Committee to Review Generic Requirements (CRGR) and will be made available in the public document room with the minutes of the 178th meeting of the CRGR.If you have any questions about this matter, please contact the NRC project manager or the technical contact listed below.Sincerely, J4~7 sLJe James G. Partlow Associate Director for Projects Office of Nuclear Reactor Regulation Enclosure:
Listing of Recently Issued Generic Letters Technical Contacts: S. Newberry, NRR (301) 492-0782 D. LaBarge, NRR (301) 492-1421 LIST OF RECENTLY ISSUED GENERIC LETTERS Generic Date of TeV canca Issued To e..k A41 Letter No. zUDJecL ---..-- ._____-._90-02 90-01 89-23 89-22 89-21 89-20 89-19 ALTERNATIVE
REQUIREMENTS
02/01/90 FOR FUEL ASSEMBLIES
IN THE DESIGN FEATURES SECTION OF TECHNICAL
SPECIFICATIONS
REQUEST FOR VOLUNTARY
01/18/90 PARTICIPATION
IN NRC REGULATORY
IMPAC SURVEY NRC STAFF RESPONSES
TO 10/23/89 QUESTIONS
PERTAINING
TO IMPLEMENTATION
OF 10 CFR PART 26 -GENERIC LETTER 89-23 POTENTIAL
FOR INCREASED
ROOF 10/19/89 LOADS AND PLANT AREA FLOOD RUNOFF DEPTH AT LICENSED NUCLEAR POWER PLANTS DUE TO RECENT CHANGE IN PROBABLE MAXIMUM PRECIPITATION
CRITERIA DEVELOPED
BY THE NATIONAL WEATHER SERVICE (GENERIC LETTER 89-22)REQUEST FOR INFORMATION
10/19/89 CONCERNING
STATUS OF IMPLEMENTATION
OF UNRESOLVED
SAFETY ISSUE (USI) REQUIREMENTS
PROTECTED
AREA LONG-TERM
09/26/89 HOUSEKEEPING
ALL LWR LICENSEES AND APPLICANTS
ALL LICENSEES
OF OPERATING
REACTORS &CONSTRUCTION
PERMITS FOR LWR NUCLEAR POWER PLANTS ALL HOLDERS OF OPERATING
LICENSEES AND CONSTRUCTION
PERMITS FOR NUCLEAR POWER PLANTS ALL LICENSEES
OF OPERATING
REACTORS AND HOLDERS OF CONSTRUCTION
PERMITS (EXCEPT BYRON BRAIDWOOD, VOGTLE, SOUTH TEXAS, AND RIVER BEND)ALL HOLDERS OF OPERATING
LICENSES AND CONSTRUCTION
PERMITS FOR NUCLEAR POWER REACTORS ALL FUEL CYCLE FACILITY LICENSEES WHO POSSESS, USE, OR PROCESS FORMULA QUANTITIES
OF STRATEGIC
SPECIAL NUCLEAR MATERIAL ALL LICENSEES
OF OPERATING
REACTORS, APPLICANTS
FOR OPERATING
LICENSES AND HOLDERS OF CONSTRUCTION
PERMITS FOR LIGHT WATER REACTOR NUCLEAR POWER PLANTS REQUEST FOR ACTION RELATED TO 09/20/89 RESOLUTION
OF UNRESOLVED
SAFETY ISSUE A-47 "SAFETY IMPLICATION
OF CONTROL SYSTEMS IN LWR NUCLEAR POWER PLANTS" PURSUANT TO 10 CFR 50.54(f)
-4 -


==Backfit Discussion==
If you have any questions about this matter, please contact the NRC project manager or the technical contact listed below.
The actions described in this generic letter are relaxations of the original position taken in Generic Letter 83-28 and are not considered a backfit in accordance with NRC procedures.


An evaluation of this letter was performed in accordance with the charter of the Committee to Review Generic Requirements (CRGR) and will be made available in the public document room with the minutes of the 178th meeting of the CRGR.If you have any questions about this matter, please contact the NRC project manager or the technical contact listed below.Sincerely,) & original signed by: Gary M. Holahan James G. Partlow Associate Director for Projects Office of Nuclear Reactor Regulation Enclosure:
Sincerely,
Listing of Recently Issued Generic Letters Technical Contacts: S. Newberry, NRR (301) 492-0782 D. LaBarge, NRR (301) 492-1421 DISTRIBUTION:
                                          )&       original signed by:
Central Files NRC PDR PD0-1 Reading DLaBarge*SEE PREVIOUS PAGE FOR CONCURRENCE
                                                    Gary M. Holahan James G. Partlow Associate Director for Projects Office of Nuclear Reactor Regulation Enclosure:
:PDI-1 :PDI-1 :AEOD :PDI-1 :DRP DRSP :DST:CVogan* :DLaBarge:rsc*DAllison*  
      Listing of Recently Issued Generic Letters Technical Contacts:
RCapra* MSlosson*  
      S. Newberry, NRR
RDudley* AThadani*:2/26/90 :2/26/90 :2/26/90 :2/26/90 :2/26/90 :2/26/90 :3/1/90 DRIS DOEA / ' NR 3 PMAS:NRR BGrimes* CBerlinger*  
      (301) 492-0782 D. LaBarge, NRR
L)GPartlow:sam HSmith*3/5/90 3/6/90 3/j /90 3/9/90 OFFICIAL RECORD COPY Document Name: ALL PROJECT MGRS/GL83  
      (301) 492-1421 DISTRIBUTION:
28}}
      Central Files NRC PDR
      PD0-1 Reading DLaBarge
      *SEE PREVIOUS PAGE FOR CONCURRENCE
:PDI-1         :PDI-1       :AEOD       :PDI-1         :DRP         DRSP     :DST
:CVogan*       :DLaBarge:rsc*DAllison*   RCapra*         MSlosson*   RDudley*   AThadani*
:2/26/90       :2/26/90     :2/26/90     :2/26/90       :2/26/90     :2/26/90   :3/1/90
DRIS
BGrimes*
                DOEA       /'     NR
                CBerlinger* L)GPartlow:sam
                                          3      PMAS:NRR
                                                  HSmith*
3/5/90         3/6/90         3/j /90           3/9/90
      OFFICIAL RECORD COPY
      Document Name: ALL PROJECT MGRS/GL83 28}}


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Latest revision as of 02:54, 24 November 2019

NRC Generic Letter 1990-003: Relaxation of Staff Position in Generic Letter 83-28, Item 2.2 Part 2 Vendor Interface for Safety-Related Components
ML031140578
Person / Time
Site: Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Washington Public Power Supply System, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Clinch River  Entergy icon.png
Issue date: 03/20/1990
From: Partlow J
Office of Nuclear Reactor Regulation
To:
References
GL-83-028 GL-90-003, NUDOCS 9003140089
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^s- UNITED STATES

NUCLEAR REGULATORY COMMISSION

WASHINGTON, D. C. 20555 March 20, 1990

TO: ALL POWER REACTOR LICENSEES AND APPLICANTS

SUBJECT: RELAXATION OF STAFF POSITION IN GENERIC LETTER 83-28, ITEM 2.2 PART 2 "VENDOR INTERFACE FOR SAFETY-RELATED COMPONENTS"

(GENERIC LETTER NO. 90-03)

This letter is to clarify the staff position in Part 2 of Item 2.2 of Generic Letter 83-28 (Vendor Interface for Safety-Related Components).

The original position reads as follows:

"For vendor interface, licensees and applicants shall establish, implement and maintain a continuing program to ensure that vendor information for safety-related components is complete, current and controlled throughout the life of their plants, and is appropriately referenced or incorporated in plant instructions and procedures. Vendors of safety-related equipment should be contacted and an interface established. Where vendors cannot be identified, have gone out of business, or will not supply information, the licensee or applicant shall assure that sufficient attention is paid to equipment maintenance, replacement, and repair, to compensate for the lack of vendor backup, to assure reliability commensurate with its safety function (GDC-1). The program shall be closely coupled with action 2.2.1 (equipment classification). The program shall include periodic communication with vendors to assure that all applicable information has been received.

The program should use a system of positive feedback with vendors for mailings containing technical information. This could be accomplished by licensee acknowledgement for receipt of technical mailings. It shall also define the interface and division of responsibilities among the licensee and the nuclear and non-nuclear divisions of their vendors that provide service on safety-related equipment to assure that requisite control of and applicable instructions for maintenance work on safety-related equipment are provided."

Since this position was established, the industry has generally taken the position that the Vendor Equipment Technical Information Program (VETIP)

described in the Nuclear Utility Task Action Committee (NUTAC) Report, INPO

84-010 issued in March 1984, meets the intent of Generic Letter 83-28, Item 2.2 Part 2.- The VETIP program includes the Nuclear Plant Reliability Data System (NPRDS) and the Significant Event Evaluation and Information Network (SEE-IN), both managed by INPO. It also includes existing programs the utilities now conduct with vendors. In particular, it includes interaction with the NSSS vendor.

90031 40089

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The staff has reviewed the VETIP program and has had the benefit of considerable discussions with licensees regarding vendor interface. It is now recognized that implementing a formal vendor interface program for every safety-related component is not practical. It is also recognized that vendors may not always be in the best position to analyze a failure because they may not be aware of the components' application, environment or maintenance history. Therefore, we conclude that the elements of VETIP

provide a framework to improve the quality and availability of equipment technical information for use by utility licensees.

Experience has shown that many vendors, in addition to NSSS vendors, do produce valuable information relating to their equipment. For this reason, the staff concludes that an adequate vendor interface program should include:

(a) A program with the NSSS vendor as described in the VETIP, which covers all the safety-related components within the NSSS scope of supply. This program should include provisions for assuring receipt by the licensee/applicant of all technical information provided by the NSSS vendor; and (b) A program of periodic contact with the vendors of other key safety-related components not included in (a) above.

The vendor interface program should also take into account the requirements of

10 CFR Part 50, Appendix B which requires the licensee or applicant to be responsible for establishing and executing the quality assurance program. It states that the licensee or applicant may delegate to others the work of establishing and executing the quality assurance program or any part of it, but the licensee or applicant shall retain responsibility for the program.

Therefore, the licensee or applicant should have a program which assures that procedures and instructions are properly prepared and implemented and that quality assurance programs for design, maintenance or modification work performed on safety-related equipment by outside vendors or contractors are properly implemented. These programs should clearly establish and delineate in writing the authority and duties of persons and organizations performing activities affecting this safety-related equipment.

The programs in (a) above should provide for the licensee or applicant to receive all updates to instruction and maintenance manuals, technical information bulletins, revised test procedures, and updated replacement parts information. The programs should include provisions which ensure the licensee receives all such vendor issued information pertinent to its safety-related equipment.

The program described in (b) above is not intended to be as extensive as the program in (a), but is intended to be a good faith, documented effort to periodically contact the vendors of key, safety-related components (such as auxiliary feedwater pumps, batteries, inverters, battery chargers, cooling water pumps and valve operators), not already included in the interface program of la) above, to obtain any technical information applicable to this

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equipment. Documented periodic contact via telephone is sufficient. It is expected that a reasonable and prudent review of operating experience, availability of vendor information, and component safety significance using insights obtained from generic or plant specific probabilistic risk analyses will yield a set of component vendors that will make up each licensee's program. In the event that vendors have gone out of business, cannot be identified, or will not supply information, the licensee or applicant should implement or continue to maintain a program that will assure that sufficient attention is paid to equipment maintenance, replacement, and repair to compensate for the lack of vendor backup such that equipment reliability commensurate with its safety function is assured.

Licensees and applicants are requested to review their present vendor interface programs and modify their programs as necessary to assure that both of the elements set out above are met. Pursuant to Section 182 of the Atomic Energy Act and 10 CFR 50.54(f), the NRC requires that licensees report to the NRC

within 180 days of receipt of this generic letter whether or not they have taken the actions requested.

Licensees undertaking the actions requested should confirm that they have examined their vendor interface programs, that their programs either already include both of the elements set out in this letter or that the elements have been scheduled for implementation. If licensee actions are not complete at the time of their submittal, the licensee should submit a completion date for the remaining actions to be taken. If the licensee declines to undertake the actions requested by this letter, the licensee is required to provide justifi- cation for the position.

The response to this letter is to be provided under oath or affirmation and is necessary to enable the Commission to determine whether or not your license should be modified, suspended, or revoked. The response shall be addressed to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D. C. 20555. The NRC will continue to monitor the effectiveness of licensee or applicant vendor interface program implementation through the inspection process and will use the responses to this letter to plan and locate resources for inspections. Where a licensee's failure to (1) obtain information from vendors, (2) evaluate information obtained from vendors, or

(3) implement necessary actions based on information obtained from a vendor results in conditions adverse to quality, the NRC will make findings and take action in accordance with its regulations.

This request is covered by the Office of Management and Budget Clearance Number

3150-0011, which expires January 31, 1991. The estimated average burden hours is 320 person hours per licensee response (144 person hours per year per licensee thereafter), including assessment of the new recommendations, searching data sources, gathering and analyzing the data, and preparing the required letters. Send comments regarding this burden estimate or any other aspect of this collection of information, including suggestions for reduting this burden, to the Records and Reports Management Branch, (MNBB-7714) Division of Information Support Services, Office of Information Resources Management, U.S. Nuclear Regulatory Commission, Washington, D. C. 20555; and to the Paperwork Reduction Project (3150-0011), Office of Management and Budget, Washington, D. C. 20503.

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Backfit Discussion

The actions described in this generic letter are relaxations of the original position taken in Generic Letter 83-28 and are not considered a backfit in accordance with NRC procedures. An evaluation of this letter was performed in accordance with the charter of the Committee to Review Generic Requirements (CRGR) and will be made available in the public document room with the minutes of the 178th meeting of the CRGR.

If you have any questions about this matter, please contact the NRC project manager or the technical contact listed below.

Sincerely, J4~7 sLJe James G. Partlow Associate Director for Projects Office of Nuclear Reactor Regulation Enclosure:

Listing of Recently Issued Generic Letters Technical Contacts:

S. Newberry, NRR

(301) 492-0782 D. LaBarge, NRR

(301) 492-1421

LIST OF RECENTLY ISSUED GENERIC LETTERS

Generic Date of A41 TeVcanca Issued To Letter No. e..k zUDJecL ---..-- ._____-._

ALTERNATIVE REQUIREMENTS 02/01/90 ALL LWR LICENSEES

90-02 FOR FUEL ASSEMBLIES IN THE AND APPLICANTS

DESIGN FEATURES SECTION OF

TECHNICAL SPECIFICATIONS

90-01 REQUEST FOR VOLUNTARY 01/18/90 ALL LICENSEES OF

PARTICIPATION IN NRC OPERATING REACTORS &

REGULATORY IMPAC SURVEY CONSTRUCTION PERMITS

FOR LWR NUCLEAR POWER

PLANTS

89-23 NRC STAFF RESPONSES TO 10/23/89 ALL HOLDERS OF

QUESTIONS PERTAINING TO OPERATING LICENSEES

IMPLEMENTATION OF 10 CFR AND CONSTRUCTION

PART 26 - GENERIC LETTER PERMITS FOR NUCLEAR

89-23 POWER PLANTS

89-22 POTENTIAL FOR INCREASED ROOF 10/19/89 ALL LICENSEES OF

LOADS AND PLANT AREA FLOOD OPERATING REACTORS AND

RUNOFF DEPTH AT LICENSED HOLDERS OF CONSTRUCTION

NUCLEAR POWER PLANTS DUE TO PERMITS (EXCEPT BYRON

RECENT CHANGE IN PROBABLE BRAIDWOOD, VOGTLE,

MAXIMUM PRECIPITATION SOUTH TEXAS, AND RIVER

CRITERIA DEVELOPED BY THE BEND)

NATIONAL WEATHER SERVICE

(GENERIC LETTER 89-22)

89-21 REQUEST FOR INFORMATION 10/19/89 ALL HOLDERS OF

CONCERNING STATUS OF OPERATING LICENSES

IMPLEMENTATION OF UNRESOLVED AND CONSTRUCTION

SAFETY ISSUE (USI) REQUIREMENTS PERMITS FOR NUCLEAR

POWER REACTORS

89-20 PROTECTED AREA LONG-TERM 09/26/89 ALL FUEL CYCLE

HOUSEKEEPING FACILITY LICENSEES

WHO POSSESS, USE,

OR PROCESS FORMULA

QUANTITIES OF

STRATEGIC SPECIAL

NUCLEAR MATERIAL

89-19 REQUEST FOR ACTION RELATED TO 09/20/89 ALL LICENSEES OF

RESOLUTION OF UNRESOLVED OPERATING REACTORS,

SAFETY ISSUE A-47 "SAFETY APPLICANTS FOR

IMPLICATION OF CONTROL OPERATING LICENSES

SYSTEMS IN LWR NUCLEAR AND HOLDERS OF

POWER PLANTS" PURSUANT TO CONSTRUCTION PERMITS

10 CFR 50.54(f) FOR LIGHT WATER

REACTOR NUCLEAR

POWER PLANTS

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Backfit Discussion

The actions described in this generic letter are relaxations of the original position taken in Generic Letter 83-28 and are not considered a backfit in accordance with NRC procedures. An evaluation of this letter was performed in accordance with the charter of the Committee to Review Generic Requirements (CRGR) and will be made available in the public document room with the minutes of the 178th meeting of the CRGR.

If you have any questions about this matter, please contact the NRC project manager or the technical contact listed below.

Sincerely,

)& original signed by:

Gary M. Holahan James G. Partlow Associate Director for Projects Office of Nuclear Reactor Regulation Enclosure:

Listing of Recently Issued Generic Letters Technical Contacts:

S. Newberry, NRR

(301) 492-0782 D. LaBarge, NRR

(301) 492-1421 DISTRIBUTION:

Central Files NRC PDR

PD0-1 Reading DLaBarge

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2/26/90 :2/26/90 :2/26/90 :2/26/90 :2/26/90 :2/26/90 :3/1/90

DRIS

BGrimes*

DOEA /' NR

CBerlinger* L)GPartlow:sam

3 PMAS:NRR

HSmith*

3/5/90 3/6/90 3/j /90 3/9/90

OFFICIAL RECORD COPY

Document Name: ALL PROJECT MGRS/GL83 28

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