ML17284A797: Difference between revisions
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PAGE WASHINGTON PUBLIC POWER kN SUPPLY SYSTEM 1-2 OPERATIONAL 28 QUALITYASSURANCE PROGIUAI DESCRIPTION | PAGE WASHINGTON PUBLIC POWER kN SUPPLY SYSTEM 1-2 OPERATIONAL 28 QUALITYASSURANCE PROGIUAI DESCRIPTION 1.3.2 The Vi P iden Nucl r reports to the chief Executive Officer and is responsible for: | ||
1.3.2 The Vi P iden Nucl r reports to the chief Executive Officer and is responsible for: | |||
0 Safe and efficient operation of Supply System nuclear power plants. | 0 Safe and efficient operation of Supply System nuclear power plants. | ||
Safe and successful completion of initial testing activities for WNP-2 (through the WNP-2 Plant General Manager). | Safe and successful completion of initial testing activities for WNP-2 (through the WNP-2 Plant General Manager). | ||
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position are: | position are: | ||
: a. Education: Bachelors Degree or equivalent in Engineering or related science. | : a. Education: Bachelors Degree or equivalent in Engineering or related science. | ||
: b. Six (6) years experience in the field of quality assurance, or equivalent number of years of nuclear industry experience in a supervisory/management position or a combination of the two. At least two (2) years of these six years experience shall be nuclear power plant experience in the overall implementation of the quality assurance program. (This experience shall be obtained within the quality assurance | : b. Six (6) years experience in the field of quality assurance, or equivalent number of years of nuclear industry experience in a supervisory/management position or a combination of the two. At least two (2) years of these six years experience shall be nuclear power plant experience in the overall implementation of the quality assurance program. (This experience shall be obtained within the quality assurance organization.) | ||
organization.) | |||
I.2. li P m i r r li r li a1 Education: Bachelor Degree or equivalent in Engineering or a related science. | I.2. li P m i r r li r li a1 Education: Bachelor Degree or equivalent in Engineering or a related science. | ||
: b. Experience: Four (4) years experience in the field of quality assurance, or equivalent number of years of nuclear plant experience in a supervisory position, preferably at an operating nuclear plant, or a combination of the two. At least one (1) of these four (4) years of experience shall be nuclear power plant experience in the implementation of the quality assurance program. | : b. Experience: Four (4) years experience in the field of quality assurance, or equivalent number of years of nuclear plant experience in a supervisory position, preferably at an operating nuclear plant, or a combination of the two. At least one (1) of these four (4) years of experience shall be nuclear power plant experience in the implementation of the quality assurance program. | ||
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The Plant General Manager operates through the Operations Manager, Maintenance Manager, Radiation Protection Manager, and Chemistry Manager. The plant organization and functional responsibilities of key plant personnel are described in Chapter 13 of the Final Safety Analysis Report for WNP-2. | The Plant General Manager operates through the Operations Manager, Maintenance Manager, Radiation Protection Manager, and Chemistry Manager. The plant organization and functional responsibilities of key plant personnel are described in Chapter 13 of the Final Safety Analysis Report for WNP-2. | ||
1.3.2.3 Th M r l 'nin reports to the Vice President, Nuclear Operations and is responsible for nuclear training policy and implementation, fire prevention and protection training, technical maintenance of the simulator to support operator training and testing, and training records management for nuclear plant operations. | 1.3.2.3 Th M r l 'nin reports to the Vice President, Nuclear Operations and is responsible for nuclear training policy and implementation, fire prevention and protection training, technical maintenance of the simulator to support operator training and testing, and training records management for nuclear plant operations. | ||
1.3.3 | 1.3.3 | ||
~ ~ The Vice Pre iden ti n u rt/Public Inf rma fficer reports to the Chief Executive Officer and is responsible for the development and implementation of policies and programs which support operation of Supply System nuclear power plants in the areas of: | ~ ~ The Vice Pre iden ti n u rt/Public Inf rma fficer reports to the Chief Executive Officer and is responsible for the development and implementation of policies and programs which support operation of Supply System nuclear power plants in the areas of: | ||
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When the unit is operating, the Supervisors may recommend that the unit be shut 968-25060 (49I) WAOQAPBectioal.PAA | When the unit is operating, the Supervisors may recommend that the unit be shut 968-25060 (49I) WAOQAPBectioal.PAA | ||
h | h | ||
Line 670: | Line 664: | ||
96$ -25060 (4I92) OQAPDAPP.mWAOQA,PD | 96$ -25060 (4I92) OQAPDAPP.mWAOQA,PD | ||
~ < I w t"~ | ~ < I w t"~ | ||
lf. $ ; $ | lf. $ ; $ | ||
Line 691: | Line 684: | ||
I | I | ||
~, | ~, | ||
i | |||
PAGE wAruworou ruruc rowra I'llSUPPLY SYSTEM 11-3 OPERATIONAL QUALITYASSUIWNCE PROGRAM DESCRIPTION 14 | PAGE wAruworou ruruc rowra I'llSUPPLY SYSTEM 11-3 OPERATIONAL QUALITYASSUIWNCE PROGRAM DESCRIPTION 14 | ||
Line 704: | Line 697: | ||
4 II II Y I ~ 1 II lt I <<.'E>> | 4 II II Y I ~ 1 II lt I <<.'E>> | ||
olb | olb V I C I 1 11 'f + + 'I4j Pp g'$'I 4t | ||
V I C I 1 11 'f + + 'I4j Pp g'$'I 4t | |||
PAGE M SUPPLY SYSTEM WAIMlMOTONtUSLIC FOwRR II-4 OPERATIONAL QUALITYASSURANCE PROGRAM DESCRIPTION 14 This alternate to the biennial procedure review requirement shall be supported by a Quality Assurance audit of a representative sample of routine plant procedures that are used more frequently than every two years. The audit shall be conducted at least every two years to ensure the acceptability of the procedures, and to verify the procedure review and revision program is being implemented effectively. | PAGE M SUPPLY SYSTEM WAIMlMOTONtUSLIC FOwRR II-4 OPERATIONAL QUALITYASSURANCE PROGRAM DESCRIPTION 14 This alternate to the biennial procedure review requirement shall be supported by a Quality Assurance audit of a representative sample of routine plant procedures that are used more frequently than every two years. The audit shall be conducted at least every two years to ensure the acceptability of the procedures, and to verify the procedure review and revision program is being implemented effectively. | ||
Line 746: | Line 737: | ||
'W | 'W | ||
. E 2 ~, | . E 2 ~, | ||
,J~ | ,J~ | ||
+ | + | ||
Line 776: | Line 766: | ||
0 | 0 | ||
( | ( | ||
II | II | ||
~PA a | ~PA a | ||
Line 848: | Line 837: | ||
W "v ' | W "v ' | ||
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h g | h g | ||
Line 883: | Line 871: | ||
k a j I E= | k a j I E= | ||
PAGE WASNINOCON tUSLIC tO~R SUPPLY SYSTEM II-15 OPERATIONAL QUALITYASSURANCE PROGRAM DESCRIPTION 14 II.15 RE AT RY E112 REV 1 I 1 7 -" ali Assu uirmn | PAGE WASNINOCON tUSLIC tO~R SUPPLY SYSTEM II-15 OPERATIONAL QUALITYASSURANCE PROGRAM DESCRIPTION 14 II.15 RE AT RY E112 REV 1 I 1 7 -" ali Assu uirmn fr nr I fPr remn fIem n rvi fr 1 P P~Ian The Supply System will implement the Regulatory Position of Regulatory Guide 1. 123, Rev. 1 (July 1977), subject to the following: | ||
fr nr I fPr remn fIem n rvi fr 1 P P~Ian The Supply System will implement the Regulatory Position of Regulatory Guide 1. 123, Rev. 1 (July 1977), subject to the following: | |||
Section 1.3 of ANSI N45.2.13-1976: The Supply System will comply with the definition of "procurement documents" as stated in its position statement on Regulatory Guide 1.74 (February 1974). | Section 1.3 of ANSI N45.2.13-1976: The Supply System will comply with the definition of "procurement documents" as stated in its position statement on Regulatory Guide 1.74 (February 1974). | ||
II.16 RE LAT RY E 1 144 REV 1 e em r 1 - "Auditin of li A urance Pr m f r Nuclear Power Plan The Supply System will implement the Regulatory Position of Regulatory Guide 1. 144, Rev. 1 (September 1980), subject to the following: | II.16 RE LAT RY E 1 144 REV 1 e em r 1 - "Auditin of li A urance Pr m f r Nuclear Power Plan The Supply System will implement the Regulatory Position of Regulatory Guide 1. 144, Rev. 1 (September 1980), subject to the following: | ||
Line 1,180: | Line 1,166: | ||
I Ownership of Work Control Process TJ [~'~ Pvp:. I,.~,.:, ..g...,,,, ..., ....:,,...' ",: '-,D 4 c ... - ~ | I Ownership of Work Control Process TJ [~'~ Pvp:. I,.~,.:, ..g...,,,, ..., ....:,,...' ",: '-,D 4 c ... - ~ | ||
~ November 1998, Clearance Process Benchmarking o January. 1999, 4 SROs & 4 ROs to work teams | ~ November 1998, Clearance Process Benchmarking o January. 1999, 4 SROs & 4 ROs to work teams | ||
~ Operations work team member expectations to be defined | ~ Operations work team member expectations to be defined | ||
Line 1,281: | Line 1,266: | ||
Work Request Activity 900 800. | Work Request Activity 900 800. | ||
700 600 600 400 300 200 | 700 600 600 400 300 200 | ||
'1 00 0 CO CO CO CO CO CO I | '1 00 0 CO CO CO CO CO CO I | ||
CD CD Q) Ql 0) CB CD CD Ch Ch 0) O) Cl | CD CD Q) Ql 0) CB CD CD Ch Ch 0) O) Cl | ||
Line 1,330: | Line 1,314: | ||
Maintenance Performance Challen es | Maintenance Performance Challen es | ||
~ Error rate | ~ Error rate Provide more critical, real time feedback on performance | ||
Provide more critical, real time feedback on performance | |||
~ Use of training to coach techniques of procedure usage, self checking, communications & Safety | ~ Use of training to coach techniques of procedure usage, self checking, communications & Safety | ||
Line 1,363: | Line 1,345: | ||
>>>>. W 8 I" ~ | >>>>. W 8 I" ~ | ||
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I I I" IqI | I I I" IqI | ||
~ ~ | ~ ~ | ||
.~. | .~. | ||
MTN WO TASK BACKLOG (400 WO N-0 (T/B>>YESICE) <<100 PREY ENTIV E MTN. N-0 <<350 | MTN WO TASK BACKLOG (400 WO N-0 (T/B>>YESICE) <<100 PREY ENTIV E MTN. N-0 <<350 | ||
" 8>>> | " 8>>> | ||
6>>>>>tIIII:":$'fS ~-'-' ':f' | 6>>>>>tIIII:":$'fS ~-'-' ':f' | ||
Radiation Protection John Peters Assistant Manager Radiation Protection | Radiation Protection John Peters Assistant Manager Radiation Protection | ||
Line 1,387: | Line 1,366: | ||
".w - ~ > ,".!cktf<!: '.Ne?V. >>:Ri' Corrective Corrective NUCLEAR av ~ 1 | ".w - ~ > ,".!cktf<!: '.Ne?V. >>:Ri' Corrective Corrective NUCLEAR av ~ 1 | ||
.""iP!!ififi/I-:IIi Jgi;, | .""iP!!ififi/I-:IIi Jgi;, | ||
~VI: hP Action Program Action Program I ~: I ~ ~ ~ ~ | ~VI: hP Action Program Action Program I ~: I ~ ~ ~ ~ | ||
Effectiveness Timeliness SAFETY 1f~i@ '~QP 5a 5b II( A JlC ji~ JJf.:~iiA:-".Ifi! | Effectiveness Timeliness SAFETY 1f~i@ '~QP 5a 5b II( A JlC ji~ JJf.:~iiA:-".Ifi! | ||
Line 1,450: | Line 1,428: | ||
~ 772 ,FY97 INDUSTRY, MEQIAN 184:REM. | ~ 772 ,FY97 INDUSTRY, MEQIAN 184:REM. | ||
o 700 569 175 500 391 4'00 266 150 | o 700 569 175 500 391 4'00 266 150 | ||
.266 | .266 125 0 | ||
125 0 | |||
o 100 CY PERFORMANCE 865 75 50 600 0 | o 100 CY PERFORMANCE 865 75 50 600 0 | ||
rr 500 370 | rr 500 370 | ||
Line 1,484: | Line 1,460: | ||
ESTIMATE 0 | ESTIMATE 0 | ||
STATION GOALS: 100 per Non-Outage months: ". per Non-Outage month average | STATION GOALS: 100 per Non-Outage months: ". per Non-Outage month average | ||
-and- I per Outage. | -and- I per Outage. | ||
= 100 Non-Outage - and - 170 Outage (thru July - 98) | = 100 Non-Outage - and - 170 Outage (thru July - 98) | ||
Line 1,617: | Line 1,592: | ||
a {2) | a {2) | ||
CRD c ttt< r | CRD c ttt< r | ||
,9 w<<<< t SW 45>>trt.'4 g%r | ,9 w<<<< t SW 45>>trt.'4 g%r m+ %2 RNR l'"v' ttZ ~ | ||
m+ %2 RNR l'"v' ttZ ~ | |||
>+i ~ 44~. | >+i ~ 44~. | ||
NPCS t, <<hatt r 5TNC~MCQ NM R C IC 0!1 DEN <<'t rtt<<'rrr 1 A~'4c tttN'c RFW | NPCS t, <<hatt r 5TNC~MCQ NM R C IC 0!1 DEN <<'t rtt<<'rrr 1 A~'4c tttN'c RFW | ||
Line 1,680: | Line 1,653: | ||
:1 10 5 | :1 10 5 | ||
~, | ~, | ||
P. | P. | ||
0 00 CO CD Q) cn CD I | 0 00 CO CD Q) cn CD I | ||
0)I I I I C | 0)I I I I C |
Latest revision as of 08:07, 4 February 2020
ML17284A797 | |
Person / Time | |
---|---|
Site: | Columbia ![]() |
Issue date: | 02/17/1998 |
From: | WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
To: | |
Shared Package | |
ML17284A796 | List: |
References | |
WPPSS-QA-004, WPPSS-QA-004-R28, WPPSS-QA-4, WPPSS-QA-4-R28, NUDOCS 9811040078 | |
Download: ML17284A797 (254) | |
Text
OPERATIONAL QUALITYASSURANCE PROGRAM DESCRIPTION PROPOSED REVISION 29,
SUMMARY
OP CHANGES
- ATTACHMENT1 Section 1- Organization Sections 1.3.2 and 1.3.2.4 were revised to eliminate the position of Corporate Chemist. The responsibilities for this position have been transferred to the Chemistry Manager. The Chemistry Manager reports to the Plant General Manager. Eliminating the position of Corporate Chemist is not considered a reduction of commitments because there is no regulatory basis for the position.
The position of Corporate Chemist was responsible for oversight and policy and did not perform a quality or safety related function.
Section 1.3.2.1 was revised to eliminate the position of Manager, Engineering Programs. The responsibilities for this position have been transferred to the Manager, Design/Projects Engineering and Manager, Technical Services/System Engineering. The Engineering organization and functional responsibilities of key personnel are described in Chapter 13 of the Final Safety Analysis Report (FSAR) for WNP-2. Eliminating the position of Manager, Engineering Programs is not considered a reduction of commitments.
Section 1.3.2.2 was revised to eliminate the position of Planning/Scheduling/Outage Manager.
The responsibilities for this position have been transferred to the Maintenance Manager. The plant organization and functional responsibilities of key plant personnel are described in Chapter 13 of the FSAR for WNP-2. Eliminating the position of Planning/Scheduling/Outage Manager is not considered a reduction of commitments.
Section 1.3.3.1.1 minor editorial changes.
Figure 1-1 was revised to eliminate the position of Corporate Chemist.
Figure 1-2 was revised to eliminate the position of Planning/Scheduling/Outage Manager.
The changes to Section 1 do not reduce commitments because a commitment is an explicit statement to take a specific action. These changes affect the organizational structure only. The actions required to properly manage plant activities will continue to be performed. Also, these changes do not effect the Quality organization.
Section 2- Quality Assurance (QA) Program Table 2-2 was revised to add new Site Wide Procedures.
The changes to Section 2 do not reduce commitments.
Page 1 of 3
OPERATIONAL QUALITYASSURANCE PROGRAM DESCRIPTION PROPOSED REVISION 29,
SUMMARY
OF CHANGES ATTACHMENT1 Section 4 - Procurement Document Control Section 4.2.2 was revised to change the word "provide" a quality assurance program to "have" a quality assurance program.
Section 4.2.6 was revised to clarify how Quality personnel review procurement documents. The review of procurement documents by Quality personnel will be a sampling, not a 100 percent review. This change removes Quality from in-line review to maintain independence. Procurement documents will continue to receive a review by independent Procurement personnel to assure quality requirements are correctly stated, that they can be inspected and controlled, and the vendor is on the current Supply System Evaluated Supplier List.
The change in Section 4 reduces commitments.
Section 6 - Document Control Section 6.2.1.g was revised to clarify the type of documents that are considered administrative procedures, which includes Site Wide Procedures.
Section 6.2.2.b was revised to clarify that Quality personnel review administrative procedures for the activity. The purpose of Quality's review of administrative procedures is to assure inclusion of appropriate quality requirements prior to implementation. Review of individual documents such as procurement documents is covered in Section 4 and review of nonconformance reports is covered in Section 15. Quality review of the FSAR and changes thereto is being eliminated. No regulatory basis was identified that requires this review. Quality will review the administrative procedure(s) that control the FSAR, but not the document itself, unless specified by the administrative controls.
The Note listed in Section 6.2.2 was revised to remove the reference to the Test Working Group.
This group was disbanded when WNP-2 became operational.
The changes to Section 6 reduces commitments.
Section 12 - Control of Measuring and Test Equipment Section 12.4 was revised to clarify that the accuracy of calibration standards need not meet the 1/4 tolerance ifthe basis for acceptance is documented and authorized by the MATE Standards Supervisor. This clarification is consistent with NU1&G-0800, Section 12.6.
This clarification does not reduce commitments.
Page2of3
OPERATIONAL QUALITYASSURANCE PROGRAM DESCRIPTION PROPOSED REVISION 29,
SUMMARY
OF CHANGES ATTACHMENT1 Section 15 - Nonconforming Materials, Parts, or Components Section 15.2.4 was revised to clarify that Quality personnel review nonconformances on a sampling basis, not a 100 percent review. The purpose of this change is to remove Quality from in-line review to maintain independence.
The change to Section 15 reduces commitments.
Section 18 - Audits Section 18.2.3 was revised to add, "Surveillances and assessments performed by the Quality organization are performed as an integral part of the evaluation (Audit) program and provide inprocess coverage of the applicable areas to supplement the audit program."
The change to Section 18 does not reduce commitments.
Appendix I - Qualification Requirements Appendix I.2.b was revised to clarify the experience requirements for the positions of Quality Programs Supervisor or Lead, Supplier Quality. This clarification is consistent with ANSUANS-3;1-1978. There is no regulatory basis for these positions and the positions are not described in NUREG-0800.
This change does not reduce commitments.
Appendix II- Position Statements Appendix II.10.b was revised to clarify that surveillances or assessments can be used to evaluate the use of supervisors as design verifiers to guard against abuse.
This change does not reduce commitments.
Appendix II.12.4 was added to clarify how Quality Assurance records may be maintained in temporary storage until transferred to the permanent plant file.
This change does not reduce commitments.
Appendix III- Additional Quality Program Requirements Appendix III.2.1.1, was revised to eliminate the Planning/Scheduling/Outage representation on the Plant Operations Committee (POC).
This change reduces commitments.
Page3 of3
OPERATIONAL QUALITYASS CE PROGRAM DESCRIPTION (WPPSS-QA-004)
APPROVED: z -j 7-Va Manager, Quality Date Effective REVISION NO. 28 ORIGINAL ISSUE: May 10, 1978 WASHINGTON PUBLIC POWBR 4> Su. I LV SYSTEM 98ii040078 'PSi023 PDR ADQCK 05000$ 97 P PDR
PAGE WASHINGTON PUBLIC POWBR 4N SUPPLY SYSTEM OPERATIONAL 28 QUALITYASSURANCE PROGRAM DESCRIPTION I F EFFE PA
~PA E'EVISIO 28 28 IV 28 1-1 12 28 2 2-4 19 3 3-2 4-1 & 4-2 5-1
.6 6-3 7 7-2 8-1 & 8-2 9-1 & 9-2 10-1 & 10-2 11-1 & 11-2 12-1 & 12-2 13-1 10 14-1 15-1 & 15-2 16-1 17-1 & 17-2 18-1 13 15 13 9QL25060 (4/92)
0 WASHLNGTON PUB LlC POWER lv 4N SUPPLY SYSTEM OPERATIONAL . 28 QUALITYASSVRA&tCE PROGRAM DESCRIPTION TBE F
~SE I~O N/A Approval Page N/A Management Statement N/A List of Effective Pages N/A 'Ihble of Contents 1 ORGANIZATION QUALITYASSURANCE (QA) PROGRAM DESIGN CONTROL PROCUREMENT DOCUMENT CONTROL 5 INSTRUCTIONS, PROCEDURES, AND DRAWINGS 6' DOCUMENT CONTROL CONTROL OF PURCHASED MATERIAL,EQUIPMENT, AND SERVICES IDENTIFICATIONAND CONTROL OF MATERIALS, PARTS, AND COMPONENTS CONTROL OF SPECIAL PROCESSES 10 INSPECTION TEST CONTROL 12 CONTROL OF MEASURING AND TEST EQUIPMENT 13 HANDLING, SIORAGE, AND SHIPPING 14 INSPECTION, TEST, AND OPERATING STATUS 15 NONCONFORMING MATERIALS, PAKE, OR COMPONENTS 16 CORRECTIVE AC&ON 17 UALITYASSURANCE RECORDS 18 AUDITS APPENDIX I QUALIFICATIONREQUIREMENTS APPENDIX II "POSITION STATEMENTS" APPENDIX III ADDITIONALQUALITYPROGRAM REQUIREMENTS 968-25060 (4/92)
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WASHINOTON PVBLIC PONi'BR 4N SUPPLY SYSTEM OPERATIONAL 28 UALITYASSU1VWCE PROGRAM DESCRIPTION R A ZATI 1.1 ~PK~PSE This section provides a description of the authorities and responsibilities assigned to Supply System organizational units and individuals involved in establishing, implementing, verifying implementation, and measuring the overall effectiveness of the administrative controls and quality assurance program during the initial testing (pre-operational and startup testing) and subsequent operations phases of Supply System nuclear power plants.
1.2 PLY Y TEM R A ZATI The Supply System organization responsible for establishing, implementing, verifying implementation, and measuring the overall effectiveness of the administrative controls and quality assurance program for its nuclear power plants is as depicted in Figures 1-1 and 1-2.
Portions of these activities may be delegated to external organizations qualified to the requirements of this Operational QA Program, hereafter referred to as QA Program; however, the responsibility shall remain with the Supply System.
1.3 MANA EME R P IBIL 1.3.1 Th hi f Ex ffi r is responsible for the establishment of policies and for overall management of Supply System operations. The Chief Executive Officer has issued a Management Statement which commits the Supply System to design, construct, and operate its nuclear power plants without jeopardy to the health and safety of the public, The Chief Executive Officer has the responsibilities as the Chief Nuclear Officer, is the ultimate Supply System authority on matters involving Plant Nuclear Safety and Quality, and appoints the members of the Corporate Nuclear Safety Review Board (CNSRB), including the Chairman and Alternate Chairman. The Chief Nuclear Officer operates through the Vice President, Nuclear Operations; Vice President, Operations Support/Public Information Officer; and Vice President, Administration/Chief Financial Officer, to provide for engineering, construction, procurement, quality assurance/quality control, and operations activities for Supply System nuclear power plants.
968-25060 (4/9I) VAEOQhRSectioal.PAA
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PAGE WASHINGTON PUBLIC POWER kN SUPPLY SYSTEM 1-2 OPERATIONAL 28 QUALITYASSURANCE PROGIUAI DESCRIPTION 1.3.2 The Vi P iden Nucl r reports to the chief Executive Officer and is responsible for:
0 Safe and efficient operation of Supply System nuclear power plants.
Safe and successful completion of initial testing activities for WNP-2 (through the WNP-2 Plant General Manager).
Establishing and monitoring maintenance systems common to operational nuclear power plants.
Training of nuclear plant staff and support personnel.
Development of programs and procedures to ensure uniform application at operational nuclear power plants.
Radiological protection, fire protection, and radioactive waste management.
0 Engineering design and analysis support for WNP-2.
'Ib accomplish this role, the Vice President, Nuclear Operations operates through the Plant General Manager; Engineering General Manager; Manager, Nuclear 'Gaining; and Corporate Chemist. I 1.3.2.1 The En ineerin eneral Mana er reports to the Vice President, Nuclear Operations and is responsible for providing project engineering and design control, nuclear fuel supply, and maintenance/operation engineering support as required for WNP-2. The Engineering General Manager is specifically responsible for:
Developing, maintaining, and implementing design control programs and processes by which plant design, and design changes, and modifications are defined, controlled, and verified.
Developing and maintaining programs for in-service inspection, and materials and welding engineering.
Providing engineering support for technical resolution of nuclear safety and licensing issues.
~ Maintaining a c'urrent engineering data base for WNP-2.
Implementing configuration control by establishing site-specific policy, procedures, and methods that allow control and accountability.
968-26060 (4/92) %AOQAHScctioaI.PAA
i' 4 e~ is PAGE WASHINGTON PUBLIC POWER 1-3 AYE SUPPLY SYSTEM OPERATIONAL 28 UALITYASSURANCE PROGRAM DESCRIFI'ION
~ Management of major plant modifications, major maintenance tasks, and contractor support.
The supply;engineering;and o efficient in-core management of nuclear fuel.
Transient analysis and licensing issue resolution to support technical specification changes and reload fuel licensing.
Reliability and availability analysis to improve plant performance, safety, and maintainability.
Developing and maintaining fire protection programs.
Training and qualification of engineering and technical support staff.
The Engineering General Manager operates through the Manager, Design/Projects Engineering; Manager, Engineering Programs; Manager, 'Ibchnical Services/ Systems Engineering; and Manager, Reactor/Fuels Engineering. The Engineering organization and functional responsibilities of key personnel are described in Chapter 13 of the Final Safety Analysis Report for WNP-2.
1.3.2.2 Th Pl n n M r for WNP-2 reports to the Vice President, Nuclear Operations and is directly responsible for safe and efficient operation of the plant in accordance with the requirements of the Operating License, the Plant 'Ibchnical Specifications, and the Plant Procedures Manual. Some of the specific'responsibilities of the Plant General Manager aic:
~ Planning, coordinating, and directing all test, operation, modification, inspection, maintenance, and refueling activities subsequent to the issuance of an Operating License.
Authorizing all plant modifications subsequent to the issuance of an Operating License.
Qualifying and training plant staff.
V Ensuring calibrated measuring and test equipment (including installed instruments covered by the Plant 'Ibchnical Specifications) is utilized at WNP-2.
Dispositioning of nonconforming items.
~ Implementing the in-service testing program.
e Implementing a fire protection program.
968-25060 (4/92) WhOQABScctioal. P&A
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PAGE WASHINGTON PVBLIC POWBR kN SUPPLY SYSTEM OPERATIONAL 28 UALITYASSURANCE PROGRAM DESCRIPTION Off-Site Dose Calculation Manual (ODCM).
The Radiological Environmental Monitoring Program and Bioassay Program.
Environmental sciences function which performs nonradiological monitoring and fitness for duty chemical analysis.
The Plant General Manager operates through the Operations Manager,'Maintenance Manager, Radiation Protection Manager, Chemistry Manager, and Planning/
Scheduling/Outage Manager., The plant organization and functional responsibilities of key plant personnel are described in Chapter 13 of the Final Safety Analysis Report for WNP-2.
1.3.2.3 The M na er cl r inin reports to the Vice President, Nuclear Operations and is responsible for nuclear training policy and implementation, fire prevention and protection training, technical maintenance of the simulator to support operator training and testing, and training records management for nuclear plant operations.
1.3.2.4
~ ~ The te hemi reports to the Vice President, Nuclear Operations and is responsible
~
for policy development, oversight, and integration of matters pertaining to chemistry at WNP-2. ~
1.3.3 Th Vi P i n i P li I f i n ffi r reports to the Chief Executive Officer and is icsponsible for the development and implementation of policies and programs which support operation of Supply System nuclear power plants in the areas of:
Quality Assurance program definition, implementation and effectiveness.
Maintaining cognizance of changing regulatory requirements and providing controlled interface between the Supply System and regulatory agencies to assure that commitment documents receive the necessary degree and depth of reviews prior to transmittal.
Providing licensing support functions in such areas as acquisition and maintenance of nuclear power plant construction permits and operating licenses.
~ Safeguards, physical plant security and fitness for duty.
o Emergency preparedness, safety and health.
Procurement, inventory, spare parts engineering, vendor quality, and warehousing.
968-25060 (430) VAEOQAPScctioal.P&h
P 44 oU ~
PAGE WASHINGTON ioUBLIC POWBR kN SUPPLY SYSTEM 1-5 OPERATIONAL 28 QUALITYASSURANCE PROGIUAl DESCRIPTION Reviewing in-house and external events for determination of cause and necessary corrective action to minimize potential for recurrence at Supply System nuclear facilities.
Establishing, managing, and administering the implementation and effectiveness of the Nuclear Safety Issues Program (NSIP).
'Ib accomplish this role, the Vice President operates through the Manager, Quality Manager, Regulatory Affairs; Manager, Security; and Manager, Procurement.
1.3.3.1 ~Th*M O1 p O M P 1dpp ,' pp IPIO dd 31 13 responsible for the definition, direction, and effectiveness of the overall Quality Assurance Program during design, construction, and operation phases of all Supply System nuclear power plants. Major functions of the Quality organization are:
Establishing and maintaining assurance programs, Nuclear Operation Standards, and department procedures and instructions which incorporate nuclear safety considerations and comply with the Quality Assurance (QA) criteria delineated in Appendix B to 10CFR 50.
Assuring through reviews, surveillances, assessments, inspections, nondestructive examinations, and audits that Supply System and its suppliers activities are being performed in a safe and legal manner in accordance with written and approved documents which comply with applicable requirements defined by the assurance programs and Nuclear Operation Standards or Site Wide Procedures.
Assessing the overall effectiveness of assurance programs implementation, including evaluation of plant performance and reporting conclusions to the Chief Executive Officer.
Stopping unsatisfactory work and controlling further processing, delivery, or installation of nonconforming material.
Establishing and maintaining adequate and qualified assurance staffing levels.
Providing trending of deficiencies to identify areas where corrective actions have not minimized recurrence.
Establishing, maintaining, and controlling the Operational QA Program Description (WPPSS-QA-004) and the Supply System Functional Manual for Nuclear Operation.
96@25060 (492) %1OQAP1SectioaI.PAA
PAGE WASHINGTON PUBLIC POWBR 1-6 k% SUPPLV SVSTEM OPERATIONAL 28 UALITVASSURANCE PROGIU384 DESCRIPTION Certifying Supply System examination personnel for non-destructive examinations (NDE). t
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-Qualifying-and certifying-Supply System Audit Team Leaders'; QC inspection and test personnel.
Acquiring and maintaining ASME Certificates of Authorization and/or Owners Certificates.
Ensuring that a written agreement with an Authorized Inspection Agency is obtained to provide for Authorized Nuclear In-Service Inspection Services.
0 Administering the WNP-2 industry and in-plant operating experience programs.
0 Providing the Independent Safety Engineering Group (ISEG) functions for assessing programs, processes and activities of various areas and operations that affect plant nuclear safety and reliability.
o - Administering the nonconforming condition and corrective action processing including assisting the cognizant organization in evaluation and determination of the root cause for plant-related events.
~ Providing the review and concurrence of selected programs, procedures, and/or instructions affecting safety, including changes thereto, to assure that applicable quality assurance requirements have been identified and specified therein.
The Manager, Quality has effective communication channels with all Supply System senior management positions and has no duties or responsibilities unrelated to quality assurance that would prevent his full attention to Quality Assurance Program matters. 'Ib accomplish the above defined role, the Manager, Quality operates through the Supervisors, Quality Services; Supervisor, Quality Programs; and Lead, Supplier Quality.
The qualification requirements for this position are as described in Appendix I, Qualification Requirements.
A management representative from the Quality Organization is a member of the Plant Operations Committee (see Appendix III) and has sufficient authority and organizational freedom to identify problems; to initiate, recommend, or provide solutions; and to verify implementation of solutions. The representative has no duties or responsibilities unrelated to quality assurance matters and has effective communication channels with all plant supervisory and management personnel.
968-25060 (4/92) MEOQABSccdool.PAA
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PACE WASHINOTON PUBLIC POWBR 4> SUPPIV SVSrEM 1-7 OPERATIONAL 28 QUALITYASSURANCE PROGIbQVl DESCRIPTION 1.3.3.1.1 The u rvi o uali ervi reports to the Manager, Quality and are directly responsible for performing internal Supply System quality assurance functions that are necessary to verify that the QA Program is being effectively implemented. This includes maintaining a sufficient number of qualified auditors to perform QA audits, as required.
Each Supervisor has the authority and responsibility to stop unsatisfactory work and control further processing, delivery, or installation of nonconforming material.
When the unit is operating, the Supervisors may recommend that the unit be shut down; the Plant General Manager, however, has the final responsibility for the overall evaluation of all aspects and implications of shutting down the operating unit.
Qualification requirements for this position is described in Appendix I, Qualification Requirements. The Supervisors, Quality Services are specifically responsible for:
aO Verifying internal Supply System activities to assure that they are being conducted in a safe and legal manner in accordance with approved programs, plans, procedures, or instructions. Such verifications will be in the form of audits, technical assessments, or quality assurance surveillances. Included in the scope of these verifications are: (i) control zoom operations; post modification/major maintenance testing and operational tests; maintenance, modification, repair, and calibration; personnel training; and refueling activities; (ii) activities associated with satisfying technical specifications and in-service inspection and testing; (iii) activities associated with the implementation of security, fire protection, and radiological protection programs; (iv) activities including engineering, maintenance, modifications, operational problem resolution, technical support activities, and operational analysis that affect plant nuclear safety and reliability; and (v) activities related to procurement, storage and issuance of parts, materials, and services to assure implementation of QA Program and management requirements.
- b. Providing the Independent Safety Engineering Group (ISEG) functions involving:
- i. Assessing programs, processes and activities including engineering, maintenance, modifications, operational problems, technical support activities and operational analysis that affect plant nuclear safety and reliability.
ii. Assessing plant operations and performance regarding conformance to regulatory requirements.
968-25060 (4/92) N(OQhPSectioaI.PAA
PACE WASH1NOTON PUBL1C POWBR kN SUPPLY SYSTEM 1-8 OPERATIONAL 28 UALITYASSURANCE PROGRAM DESCRIPTION iii. Evaluating industry operating experience, including
-,. recommendations for improvements in overall plant performance involving plant practices, procedures and equipment.
lv. Providing certain key operating experience information to operators and other plant personnel.
1.3.3.1.2 Th rvi or uali Pr m reports to the Manager, Quality and is directly responsible for:
Administration of the nonconforming condition and corrective action program.
o In-plant QC functions and nondestructive examinations.
Certifying Supply System nondestructive examination, QC, and test personnel.
Maintaining Quality Program documents.
Qualification requirements for this position are described in Appendix I, Qualification Requirements.
1.3.3.1.3 li r li reports to the Manager, Quality and is directly responsible for the source surveillance/audit program and for assuring that items received for WNP-2 meet the required quality standards, including:
Establishing vendor witness points for inspection and release of material/
equipment for shipment.
QC receipt inspection of materials and equipment received by the Supply System.
Establishing and maintaining evaluated vendors list.
Planning, coordinating, and performing source surveillances, source inspections, and external audits to veiify'implementation of vendors'A/QC programs..
o Reviewing and approving vendor furnished QA/QC procedures and programs.
Reviewing for acceptance other utility audits furnished through the Nuclear Procurement Issues Committee (NUPIC).
Qualification requirements for this position are described in Appendix I, Qualification Requirements.
968-25060 (492) W!'L~ectionLP&A
PACE WASHINOTON PUBLIC POWBR 1-9 kW SUPPLY SYSTEM OPERATIONAL 28 QUALITYASSURANCE PROGRAM DESCRIPTION 1.3.3.2 Th M r R l Affai reports to the Vice President, Operations Support/PIO and is responsible for:
Acquiring.and maintaining-operating o -
licenses of Supply System nuclear power plants.
Defining and implementing programs which assure that licensing submittals receive an adequate technical review from cognizant Supply System, NSSS, or AE personnel prior to transmittal.
Tracking licensing commitments and taking action necessary to assure that they are being met in a timely manner.
Providing coordinated development of responses and comments to new laws, regulations, regulatory guides, and other regulatory issuances.
Developing and maintaining an emergency response program that includes plans,
~ ~ ~ ~ ~ ~
implementing procedures, training, and drills and exercises. ~
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1.3.3.3
~ ~ ~ The M n r P m n reports to the Vice President, Operations Support/PIO and is
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responsible for contracting, procurement and storage control services that support operation and maintenance of Supply System nuclear power plants, the sale and demolition of Projects WNP-3, WNP-4 and WNP-5. These responsibilities include:
Development of Supply System procurement policies and procedures.
Procurement of items and services in response to approved purchase requisitions.
~ Coding, cataloging, handling, storage, shipping, and disposal of procured items.
~ Providing project management for disposition of assets from terminated power projects and disposition of major assets surplus to operating power projects.
Maintaining the Restricted Use Equipment List (RUEL).
Providing criteria for Class 1 and commercial grade dedicated spare parts procurement.
968-25060 (4/%) 1VAOQAP8ecdon1.PAA
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- a. Education: Bachelors Degree or equivalent in Engineering or related science.
- b. Six (6) years experience in the field of quality assurance, or equivalent number of years of nuclear industry experience in a supervisory/management position or a combination of the two. At least two (2) years of these six years experience shall be nuclear power plant experience in the overall implementation of the quality assurance program. (This experience shall be obtained within the quality assurance organization.)
- b. Experience: Four (4) years experience in the field of quality assurance, or equivalent number of years of nuclear plant experience in a supervisory position, preferably at an operating nuclear plant, or a combination of the two. At least one (1) of these four (4) years of experience shall be nuclear power plant experience in the implementation of the quality assurance program.
- 1. High school diploma or GED.
- 2. . Sixty.(60).semester hours of, related technical education taught at the college level (900 classroom or instructor conducted hours).
- 3. Qualified as an NRC senior operator at the assigned plant.
- 4. Four (4) years of additional experience in his area of responsibility.
- 5. Four (4) years of supervisory or management experience.
- 6. Demonstrated ability to communicate clearly (verbally and in writing).
- 7. Certification of academic ability and knowledge by corporate management.
- 8. Successful completion of the Engineer-In-Training examination.
- 10. Associated degree in Engineering or a related science.
- a. Verifying internal Supply System activities to assure that they are being conducted in a safe and legal manner in accordance with approved programs, plans, procedures, or instructions. Such verifications willbe in the form of audits, technical assessments, or quality assurance surveillances. Included in the scope of these verifications are: (i) control room operations; post modification/major maintenance testing and operational tests; maintenance, modification, repair, and calibration; personnel training; and refueling activities; (ii) activities associated with satisfying technical specifications and in-service inspection and testing; (iii) activities associated with the implementation of security, fire protection, and radiological protection programs; (iv) activities including engineering, maintenance, modifications, operational problem resolution, technical support activities, and operational analysis that affect plant nuclear safety and reliability; and (v) activities related to procurement, storage and issuance of parts, materials, and services to assure implementation of QA Program and management requirements.
- b. Providing the Independent Safety Engineering Group (ISEG) functions involving:
- b. At the time of temporary/permanent transfer of system/component custody to 'Inst and Startup organization.
- a. Proposed changes to the QA Program will be evaluated to determine whether or not they would result in a reduction of commitments previously accepted by the Nuclear Regulatory Commission (NRC).
- b. Changes that do not reduce the commitments may be implemented prior to forwarding such changes to the NRC. However, all such changes shall be forwarded to the NRC at least annually.
- a. Operational QA Program Description.
- b. Supply System Functional Manual for Nuclear Operation.
- d. As-built documents.
- e. Final Safety Analysis Reports.
- f. Procurement documents.
- h. Nonconformance reports.
- a. Type documents listed in paragraph 6.2.1.c through 6.2.1.h are reviewed for technical adequacy, by qualified individuals, prior to approval for release.
- b. Procedures listed in paragraph 6.2.1.g are reviewed for inclusion of appropriate quality requirements and concurred with by qualified Quality personnel, prior to approval for release.
- c. Documents are approved for release by authorized personnel prior to implementation.
- d. Documents are available at the location where the prescribed activity willbe performed prior to commencing the work.
- e. Changes (other than those that are of administrative nature) to approved documents are reviewed and approved by the same organizations that performed the original review and approval unless delegated to other appropriately qualified organizations.
- a. Unique identification of the item and its traceability to the calibration test data.
- b. Labeling or tagging (or otherwise controlling) to indicate the due date of the next calibration.
- c. Calibration technique and frequency.
- d. Generation and maintenance of records which indicate the complete listing of all items under the calibration system together with their current calibration status.
- e. Controlled environment conditions for sensitive and close tolerance M&TE.
- a. Clearly identify the nonconforming item; and
- b. Describe the nonconformance, the disposition of nonconformance, and inspection/test requirements (where applicable).
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- a. Education: Bachelors Degree or equivalent in Engineering or related science.
- b. Six (6) years experience in the field of quality assurance, or equivalent number of years of nuclear industry experience in a supervisory/management position or a combination of the two. At least two (2) years of these six years experience shall be nuclear power plant experience in the overall implementation of the quality assurance program. (This experience shall be obtained within the quality assurance organization.)
- b. Experience: Four (4) years of nuclear plant experience at an operating nuclear plant. At least one (1) of these four (4) years of experience shall be in the implementation of the quality assurance program through participation in the QA or QC function, or involvement in programs subject to QA/QC audits or inspections, Equivalency will be determined based upon an evaluation of the following factors:
- 1. High school diploma or GED.
- 2. Sixty (60) semester hours of related technical education taught at the college level (900 classroom or instructor conducted hours).
- 3. Qualified as an NRC senior operator at the assigned plant.
- 4. Four (4) years of additional experience in his area of responsibility.
- 5. Four (4) years of supervisory or management experience.
- 6. Demonstrated ability to communicate clearly (verbally and in writing).
- 7. Certification of academic ability and knowledge by corporate management.
- 8. Successful completion of the Engineer-In-Training examination.
- 9. Professional Engineer License.
- 10. Associated degree in Engineering or a related science.
- 2. Section 1.1 of ANSI N45.2.4-1972: This standard will be applied to the installation, inspection, and testing of Class 1E instrumentation, electrical systems and/or components for plant modifications comparable in nature and extent to the activities normally occurring during the initial plant design and construction phase.
- 3. Section 3(3) of ANSI N45.2.4-1972: Checking of records is normally accomplished during periodic surveillances and audits of the storage facility.
- 4. Section 5.1.2 of ANSI N45.2.4-1972: Inspections to verify housekeeping will be done as stated in the Supply System position statement on Regulatory Guide 1.39.
- 5. Section 5.2.1 of ANSI N45.2.4-1972: Tests will include those listed as appropriate. The manufacturers'ecommendations shall be considered. The test procedure will specify the actual test to be performed.
- 6. Section 9 of ANSI N45.2.4-1972: The Supply System position, stated herein, does not address the codes and standards listed and/or referenced in this paragraph. Such position will be developed in the future, if the need arises.
- 7. Appendix A "Supplementary Provisions for Multi-UnitStations" to ANSI N45.2.4-1972 is not considered applicable to Supply System nuclear power plants.
- 8. Appendix B "Additional Codes, Standards and Guides" to ANSI N45.2.4-1972:
- 2. Section 5.2.13.4 of ANSI N18.7-1976/ANS-3.2: The third paragraph of this section is revised to read, "Special handling tools and equipment shall be inspected and/or tested, as necessary, in accordance with written procedures and at specific times to verify that the tools and equipment are adequately maintained."
- 3. Section 5.2.15 of ANSI N18.7-1976/ANS-3.2: The fourth paragraph of this section is replaced with the following (the remaining text of this section is unchanged):
- 4. Section 5.2. 17 of ANSI N18.7-1976/ANS-3.2 states that inspection of operating activities may be conducted by second-line supervisory personnel or by other qualified personnel not assigned first-line supervisory responsibility for conduct of the work. The Supply System position is to allow the plant supervisors to perform inspections of surveillance tests, provided that operations'irst-line an after-the-fact review of surveillance documentation is performed by the, second-line supervisor or by other personnel not assigned first-line responsibility for the conduct of the work.
- 5. Sections 5.2.19.1 and 5.2.19.2 of ANSI N18.7-1976/ANS-3.2 describe rules of practice for preoperational and startup test program. The Supply System intends to comply with the provisions of these sections. In cases, where confiicts exist between these sections and Regulatory Guide 1.68, the Supply System will comply with the implementation of Regulatory Guide 1.68 as described in Chapter 14 "Initial Test Program" of the Final Safety Analysis Report.
- 2. Regulatory Position C.5 of Regulatory Guide 1.37 (March 16, 1973) states, in part, "Specifically, tools which contain materials that could contribute to intergranular cracking or which, because of previous usage, may have become contaminated with such materials should not be used on surfaces of corrosion-resistant alloys. In clarification, the Supply System will either follow the chemical composition limits established by its Nuclear Steam Supply System (NSSS) vendor, or establish such limits based upon a documented engineering evaluation.
- 3. Section 2.1 of ANSI N45.2.1-1973 states, in part, "Planning for cleaning activities shall include a review of the system and component design specifications and drawings. In clarification of this requirement, a review of system and component design specifications and drawings will be required for only those modifications which change the design of a Quid system.
- 4. Section 2.3 of ANSI N45.2.1-1973, last sentence, is revised to read, "Test reports shall include an evaluation of the acceptability of inspection and test results and provide for identifying the individual who performed the evaluation."
- 5. Section 3.1.2.1 of ANSI N45.2.1-1973 states, in part, "Scattered areas of rust are permissible provided the aggregate area of rust does not exceed two square inches in any one square foot area." The Supply System considers this two square inch limit as a guide only. Adequate discretion by experienced personnel will be used in all cases.
- 6. Section 3.1.2.5 of ANSI N45.2.1-1973 states, in part, "There shall be no evidence of organic contamination in the efiluent water or on the filter." The Supply System intends to comply with this requirement. The presence of organic contamination will be determined visually or by feel.
- 7. Section 4 of ANSI N45.2.1-1973, second sentence, is revised to read, "Inspections, examinations, or tests for cleanliness shall be performed if it is suspected that cleanliness has been affected by transportation to, or storage at the installation site."
- 8. Section 7.4 of ANSI N45.2.1-1973 requires checking of cleaning solutions for t, .5 effectiveness of inhibitors (if used). In clarification of this requirement, the effectiveness of inhibitors (if used) will be determined by documentation in technical literature or manufacturer's or vendor's recommendations.
- 2. Section 3.5.2 of ANSI N45.2.2-1972, last sentence, is revised to read as, "Tapes used for identification rather than sealing which are not near a welding operation may remain indefinitely (see also Appendix Section 3.5.2 for additional requirements)."
- 3. Section 3.7.1 (1) of ANSI N45.2.2-1972: The Supply System may use cleated, sheathed boxes for loads up to 1,000 pounds rather than 500 pounds limit imposed here. This type of box has been tested by the WNP-2 Nuclear Steam Supply System vendor and found safe for loads up to 1,000 pounds. Other national standards allow the 1,000 pound designation (see Federal Specification PPP-B-601).
- 4. Section 6.1.2 (1) of ANSI N45.2.2-1972: Temperature and humidity controls required for storage of Level A items are not considered applicable for nuclear fuel assemblies unless recommended otherwise by the nuclear fuel manufacturer. The Supply System will abide by the manufacturer's recommendation.
- 5. Section 6.4.2 of ANSI N45.2.2 gives detailed requirements for care of items in storage. In clarification,.the Supply System will either foHow manufacturer's recommendation or follow its own requirements, established based upon a documented engineering evaluation,, concerning maintenance of protective covers, seals, and caps; maintenance of preservatives and inert atmosphere; energization of instrument racks and space heaters; insulation resistance testing; and rotation of shafts for rotating equipment.
- 6. Appendix Sections A3.4.1 (4) and A3.4.1 (5) of ANSI N45.2.2-1972: During printing of the standard, a transposition occurred between the last sentences of these sections. The Supply System will comply with the correct wording which reads as follows:
- 2. Section 1.2 of ANSVASME N45.2.6-1978, fourth paragraph, states that the requirements of this Standard apply to personnel of the owners and their suppliers. In clarification, the extent of application of the requirements of ANSUASME N45.2.6-1978 to Supply System suppliers will depend upon the nature and extent of materials or services furnished, and as further described in Supply System positions on Section 2.4 and 3 of ANSVASME N45.2.6-1978.
- 3. Section 2.1.2 of ANSUASME N45.2.6-1978 implies that personnel performing non-NDE type of inspections, examinations, and testing will be formally certified. The Supply System does not plan this formal certification. Instead, the Supply System will select such personnel to predetermined quaMcation requirements for the specific task based on their education, experience, and training. Formal training records, when used as the basis for qualification, will be maintained on file.
- 4. Section 2.4 of ANSI/ASME N45.2.6-1978 requires issuance of formal certification to individuals and specifies the details of the information to be included in the certificate. The Supply System does not plan to issue formal certificates to individuals within the scope of ANSI/ASME N45.2.6-1978 and Regulatory Guide 1.8. However, information similar to that described in this section of the Standard will be available in documented form attesting that the individual is capable of performing the assigned task(s). The Supply System will use a similar approach in evaluating supplier compliance with this section of the Standard.
- 5. Section 3 of. ANSI/ASME N45.2.6-1978 divides the capability requirements of inspection, examination, and testing personnel into three levels, namely Level I, Level II, and Level III. The Supply System will not assign these levels to its personnel performing inspection, examination, and testing activities. However, the selection of personnel for particular tasks will be such as to match the capabilities to the types of tasks and maintain the intent of the three levels.
- b. Quality Assurance audits,'surveillances, or assessments cover the frequency and effectiveness of use of supervisors as design verifiers to guard against abuse.
- 2. Section 2 of ANSI N45.2. 10-1973: The definition of "specification" is revised to read as follows:
- b. 2-hour rated file containers meeting NFPA No. 232-1975 (Class B) without additional NFPA provisions.
- d. A 2-hour fire rated facility meeting the following criteria and provisions:
- 2. Section 3.2.2 of ANSI N45.2.9-1974 is revised to read, "Index - The quality assurance records shall be indexed. The indexing system(s) shall include, as a minimum, record retention times and the location of the records within the record system. The indexing system(s) shall provide sufhcient information which can be used to identify item(s) or activity(ies)."
- 3. Section 5.4.3 of ANSI N45.2.9-1974 is revised to read, "Special Processed Records - Provisions shall be made for special processed records (such as radiographs, photographs, negatives, and microfilm) to prevent damage from excessive light, stacking, electromagnetic fields, and temperature. These provisions will be delineated in procedures and/or instructions which will incorporate, or take into consideration, available manufacturers'ecommendations.".-
- b. Use of lockable temporary storage containers with a minimum one hour fire rating and an Underwriters'aboratory (UL) label (or equivalent).
- d. Designation of a custodian with the authority to enforce the storage pI'ocedUI'es.
- e. Provisions shall be made in the storage arrangement to prevent damage from condensation.
- 2. Section 2.3 of ANSI N45.2.8-1975, last sentence is revised to read, "Test reports shall include an evaluation of the acceptability of inspection and test results and provide for identifying the individual who performed the evaluation."
- a. Review of 10CFR50.59 Safety Evaluations associated with procedures and programs required by Technical Specification 5.4 and changes thereto.
- b. Review of all proposed tests and experiments that afFect nuclear safety; 968-25060 (4/92) W:IOQAPDIOQAPDAPP.IH
- d. Review of all proposed changes or modifications to unit system or equipment that affect nuclear safety;
- e. Investigation of all violations of the Technical Specifications, including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence, to the Chief Nuclear Officer and to the Corporate Nuclear Safety Review Board; Review of all REPORTABLE EVENTS; g Review of unit operations to detect potential hazards to nuclear safety;
- h. Performance of special reviews, investigations, or analyses and reports thereon as requested by the Plant General Manager or the Corporate Nuclear Safety Review Board; Review of the Security Plan and submittal of recommended changes to the Corporate Nuclear Safety Review Board; J ~ Review of the Emergency Plan and submittal of recommended changes to the Corporate Nuclear Safety Review Board;
- k. Review of any accidental, unplanned, or uncontrolled radioactive release including the preparation of reports covering evaluation, recommendations, and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Chief Nuclear Officer and to the Corporate Nuclear Safety Review Board; and Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATIONMANUAL.
- d. prior to their implementation.
- b. Render determinations in writing with regard to whether or not each item considered under Appendix IH, 2.1.6a. through e. constitutes an unreviewed safety question as defined in 10 CFR 50.59.
- b. Nuclear engineering, C. Chemistry and radiochemistry,
- d. Metallurgy,
- e. Instrumentation and control,
- f. Radiological safety,
- g. Mechanical and electrical engineering, and
- h. Quality Assurance practices.
- b. Proposed changes to procedures, equipment, or systems which involve an unreviewed safety question as defined in 10 CFR 50.59; C. Proposed tests or experiments which involve an unreviewed safety question'as defined in 10 CFR 50.59; 968-2S060 (4/92) WAOQAPDIOQAPDAPP.III
- d. Proposed changes to Technical Specifications or the Operating License; e, Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instruction having nuclear safety significance; Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety;
- g. AllREPORTABLE EVENTS;
- h. All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety; and Reports and meeting minutes of the POC.
- b. The performance, training and quaMcations of the entire unit staff at least once per 12 months; C. The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems, or method of operation that affect nuclear safety, at least once per 6 months;
- d. The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix B, 10 CFR Part 50, at least once per 24 months;
- e. The fire protection programmatic controls including the implementing procedures at least once per 24 months by qualified licenses QA personnel; 968-25060 (4/92) W LOQAPDIOQAPDAPP.IH
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- g. The Security Plan and implementing procedures at least once per 12 months.
- h. The fire protection equipment and program implementation, at least once per 12 months utilizing either a qualified offsite licensee fire protection engineer(s) or an outside independent fire protection consultant. An outside independent fire protection consultant shall be utilized at least once every third year; and Any other area of unit operation considered appropriate by the CNSRB or the Chief Nuclear Officer.
- k. The OFFSITE DOSE CALCULATIONMANUALand implementing procedures at least once per 24 months.
- m. The performance of activities required by the Quality Assurance Program for effluent and environmental monitoring at least once per 12 months.
- a. Items identified at each CNSRB meeting that require actions shall be identified and tracked. These actions shall be resolved in a time frame commensurate with their importance to safety.
- b. Minutes of each CNSRB meeting shall be prepared, approved, and forwarded to the Chief Nuclear Ofhcer within 15 working days following each meeting.
- c. Reports of reviews encompassed by Appendix III, 2.2.7 above, shaH be prepared, approved, and forwarded to the Chief Executive Officer within 15 working days following completion of the review.
- d. Audit reports encompassed by Appendix III, 2.2.8 shall be forwarded to the Chief Nuclear Officer and to the management positions responsible for the areas audited within 30 days after completion of the audit.'.0 R ED AND PR RAM 3.1 Each procedure of Technical Specification 5.4.1, and changes thereto, shall be reviewed and approved as specified by Appendix III, 4.0, prior to implementation and reviewed periodically as set forth in administrative procedures.
- a. The intent of the original procedure is not altered;
- b. The change is approved by two members of the unit management staff, at least one of these individuals shall be the supervisor in charge of the shift and holds a Senior Operator license on the unit affected; and
- c. The change is documented and reviewed by the appropriate member(s) of Plant management, within 14 days of implementation.
- a. Records and logs of unit operation covering time interval at each power level.
- b. Records and logs of principal maintenance activities, inspections, repair, and replacement of principal items of equipment related to nuclear safety.
- d. Records of surveillance activities, inspections, and calibrations required by the Plant Technical Specifications.
- e. Records of changes made to the procedures required by Technical Specification 5.4.1.
- g. Records of sealed source and fission detector leak tests and results.
- h. Records of annual physical inventory of all sealed source material of record.
- a. Records and drawing changes refiecting unit design modifications made to systems and equipment described in the Final Safety Analysis Report (F SAR).
- b. Records of new and irradiated fuel inventory, fuel transfers, and assembly burnup histories.
- c. Records of radiation exposure for all individuals entering radiation control areas.
- d. Records of gaseous and liquid radioactive material released to the environs.
- e. Records of transient or operational cycles for those unit components identified in Technical Specification 5.5.5.
- h. Records of inservice inspections performed pursuant to the Technical Specifications.
- k. Records of meetings of the POC and the CNSRB.
- m. Records of analysis required by the radiological environmental monitoring program that would permit evaluation of the accuracy of the analysis at a later date. This should include procedures efFective at specified times and QA records showing that these procedures were followed.
- n. Records of reviews performed for changes made to the OFFSITE DOSE CALCULATIONMANUALand the PROCESS CONTROL PROGRAM.
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SUMMARY
~ Ownership of Human Performance is evident and measurable.
~ Staffing levels recovered
~ Supervisory team strengthened through new licenses
~ Operations leadership and focus evident
Conclusions
~ CHALLENGES
~ Performance in Training
~ Step change in work process involvement and performance
~ Change management associated with newly licensed individuals
~ Supervisor ownership and accountability o Continued improvement in human performance
Maintenance Gary Weimer Work Team Manager (Team 4}
Management Vision An efficient process that results in a safe and reliable plant
I Key PSA Areas of Interest
~ Maintenance Backlog
~ Work Teams
~ Maintenance Performance
Backlog Reduction Positi yes Backlog has stabilized, even though:
>>Forced Outage
>>More WR's written since FP event
Backlog Reduction Challen es Reduce Backlog to level where emergent work is backlog work (shorter cycle time}:
>>Improve Planning
>>More planner resources
>>Reduce rework (assessing)
>>Improve tool availability
>> Eliminate scheduling roadblocks
Work Request Activity 900 800.
700 600 600 400 300 200
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Non-Outage Maintenance qV tq' f' V 'at *'4 =7 + \ v Work Order Task Backlog 1000 900 800 700 o 600 500 400 .
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Work Teams Positi yes
~ Single focal point for planning, scheduling and conduct of maintenance activities
~ Incorporated WIN team members (and experience/attitude} into new work teams-
'eginning to infuse Operations focus into maintenance activities.
~ Reduced time to resolve work order concerns
Work Teams Challen es Reduce Backlog
>> More effectively use training to improve team performance
>> Complete team structure. Incorporate Operations RO and SRO into work teams
Maintenance Performance Positi yes
~ Schedule adherence is improved
~ PER initiation criteria eliminated and WR threshold reduced:
>>writing schedule delay PER's
>>raising niore materiel concerns
~ Training improvement plan in place
Maintenance Performance Challen es
~ Error rate Provide more critical, real time feedback on performance
~ Use of training to coach techniques of procedure usage, self checking, communications & Safety
Schedule Activity hl 0 "' ~ ~t ~4P t"~ 1 WNP-2 DAILYSCHEDULING PROCESS INDICATORS Report Date: November 2, 1998 or ee earn earn earn earn earn earn earn earn ee eginnIng annlng omp e e I I' .I"
~
o ngineenng ec o s ea rance evtews or on ro eviews ec a evIews s repare a owns omp e e as vaja e ea y o or aus mp m c e ec <veness C" ~.
'F 4".t', ' pe
~ ~
g$rq !.~H~g +Oj, $ UNAVAILABLE C 0 0 0 0 0 0 0 0
0 Maintenance Self Assessments COMPLETED
~ Post R13, incl Foreign Material Control
~ Standards Lab
~ HVAC Program
~ Passport Baseline
~ Work Control/Implementation Process SCHEDULED
~ Preventive Maintenance
~ Work Team Effectiveness
~ Rework Program
~ Work Control/Implementation Process
Maintenance
. ~" ",' '": ~ -.. "!':I': '4.p'P'I'"J ( >" ';....'!."'" .';:
LOST TIME ACCIDENTS ~ 0 RECORDABLE ACCIDENTS ~ 0 MAINTENANCEEXPOSURE (mR) u Nov Nov 1 Ind.21 2 Ind.22
~, '.. '... >'>>'>>>>, .' Js t'HAd Lp>>.I I>>>. g>I>> .~ >~< ~I,W".L '>>>I',.' >>>>>'>> <<" >>"
'ct L
PERSONNEL ERROR RATE <<.30 GOLD CARDS (P/M) OBSERVATIONS <<40 Aug Oct Aug .. 5-
' 39
- 0. 37% 0.31% 29
>>>>. W 8 I" ~
IIII,. II,-;I;;!!I'.
';i";tv)I~ ~ >>> '>>y '
I I I" IqI
~ ~
.~.
MTN WO TASK BACKLOG (400 WO N-0 (T/B>>YESICE) <<100 PREY ENTIV E MTN. N-0 <<350
" 8>>>
6>>>>>tIIII:":$'fS ~-'-' ':f'
Radiation Protection John Peters Assistant Manager Radiation Protection
~ ~
Radiation Protection PSA Focus
~ Supervisory oversight and involvement
~ Radiation exposure and contaminations
~ Corrective Action Program
~ Radiation Protection culture
Radiation Protection Performance Indicator Annunciator Panel October 1998
>Q/ S i/li a a c:t <<I'x-'p
".w - ~ > ,".!cktf<!: '.Ne?V. >>:Ri' Corrective Corrective NUCLEAR av ~ 1
.""iP!!ififi/I-:IIi Jgi;,
~VI: hP Action Program Action Program I ~: I ~ ~ ~ ~
Effectiveness Timeliness SAFETY 1f~i@ '~QP 5a 5b II( A JlC ji~ JJf.:~iiA:-".Ifi!
2 J.'
i' drjiJ(JItAJ<Jg,"'t."
'in~~@%%
HUMAN PERFORMANCE
~ i ~
~ '
A
~
ip '.sg '
MONTHLY Monthly Performance Rating PERFORMANCE October 1998 = 2.2 3.1 3.0 2.3 Plant > 1A9 > 2.49 '~~~~~.,>,~;.",,"
~
MATERIAL Contaminated Areas 3 2.2 CONDITION 13 Improvement Needed Less than Monthly Expectatlon = 3 pts KEY Satisfactory Performance Meets Previous 3 months Monthly Expectatlon = 2 pts a¹RcA' a e Ã" ~'dP:.f I'i Pf 'QJ jk~jQ+J/ggJ]/~QAJ~yJ/ j9JJI I/l~fI!if."
'u/rani P~/bff/Iilfic Monthly Rating = 2.5 q'i'verage (since March 98)
Indicator ¹ Responsible Indlvldual Rcv 1 - 12/3/98
Total PER's by Department QA PSO
- a n PA OZa~
RIA EP SEC SS TRN o199S o 1996 g 1997 o 1998 ytd
Radiation Protection Annunciator 410 - October 1998 Supervisor Time In-Field 600
'517.2 ~ ~
500 400 370 288.2I 300
'!! >)C,l!. dt!'"
233 200 152.9c 97.8.
138.2 100 0
CO CQ CO CO CO CD CD CD CD CD C C O. O CO CL co
~HOURS IN FIELD GOAL: 216 hours0.0025 days <br />0.06 hours <br />3.571429e-4 weeks <br />8.2188e-5 months <br /> per month for 10 RP Manager/Supervisors. Res ons!bio Indnndual. L Ree POSITIVE SATISFACTORY NEEDS IMPROVEMENT ADVERSE WHITE YELLOW cia <<,N f."p';.~ i'm- .!I i ~ t
',.':Y&r!- !"'p'i~'" >V
) 194 ) 173
Radiation Protection Annunciator 413 - October 1998 Plant Contamination: Percent Floor Space & Number of C-Zones 1 0 100 90 80
'77*.
71 70 67 6 60 6
2 5 5:5 50 0n O
0 0
'Z
- 0. 4 40 m 3
30 20
.1.9 - 1.9 1.9 10 0 0 CO CO CO CO CO CO CQ cr cn Qr Qr err Qr Ch I
rrl 0 O V rrr er ru O
eie CONTAMINATEDAREA e3 NUMBER OF CZONES REMARKS: Total RCA Space: 369,488 ft (approximate) Contaminated Floor Space for month ending August: 1.9% or 7047 ft2(approximate)
See Annuciator 13a for details Res nsihle Individual: M She herd POSITIVE SATISFACTORY NEEDSIMPROVEMENT ADVERSE WHITE YELLOW (2% (5%
Radiation Protection Annunciator 05b - October 1998 Corrective Action Program Effectiveness CY98 C
0 0 0
CO CO CO CO Ol cn Ol CD Cl C CD Cl
~ NUMBER OF REPEAT EVENTS CRITERIA: This performance measure monitors the results of the Radiation Protection review of PER dispositions and the number of PER's written on 'Repeat Events.' repeat event is defined as an issue that reoccurred in the last 2 years and all corrective actions from the previous event are in place.
REMARKS: PER 298-1581documents a repeat issue dealing with the improper release of personal items and tools from the RCA. An immediate corrective action was put in place to provide management observations of personnel access practices and provide results of those observations to RP Operations.
Res onsible IndiVidual: JF Peters POSITIVE SATISFACTORY NEEDS IMPROVEMENT ADVERSE WHITE YELLOW 1 2
0 Radiation Protection Annunciator ¹5a - October 1998 Corrective Action Program Timeliness - CY98 r4 c -'cc1 1'". \<C > '<".'+V c H ~ 1 10 3
2 DATAIN AVAIIA 0
CO CO CO CO CO CO CO cn cn1 cn cn Ol cn Ol C C CL O CC CL O Cl l 7 CO
~NUMBER OF CAP's DEFINITION: This performance measure monitors the average number of Corrective Action Program Dispositions and Corrective Program Actions (CAPS) that are late throughout the month. Quality Program's report is the data source.
Res nsible individual: JF Pelers POSITIVE SATISFACTORY NEEDSIMPROVEMENT ADVERSE WHITE YELLOW 1 late 2 late
Radiation Protection Annunciator N - November 1998 Collective Radiation Exposure - FY99
~ & Q 7 FY PERFORMANCE 1000 200 900 800
~ 772 ,FY97 INDUSTRY, MEQIAN 184:REM.
o 700 569 175 500 391 4'00 266 150
.266 125 0
o 100 CY PERFORMANCE 865 75 50 600 0
rr 500 370
- o. 4' 25 248 5 7,8 '.1 4.3 0 CLI cn CO CO CO CO CO CO 0) G) 0)I CB cn rn
- 0) cn o) c) 0)I G) cn cn cnI R e O O O
rn r
CO Cr. ro c 0 0 Co Z O CO 0 FY MONTHLYPERFORMANCE 0FY MONTHLYGOAL REMARKS: Monthly Goal 4.5 REM, Actual 3.9REM. RED annuciator based on >10 FYTD Goal (22.5 REM goal to date, 25.2 REM actual to date)
InforrnaIion Provided by: K Spero WHITE YELLOW
'.".- '~Il~g fir'I~.' eXpeCted -Or- < FYTD gOal < expected -or- ) FYTD goal
WNP-2 Radiation Protection r ~r Radiation Protection Manager Asst Radiation Protection Manager Administrative Assistant Radiological Ops Radiological Planning Radiological Support Supervisor Supervisor Supervisor HP Craft Supervisors~ Radiological Planning Staff Dosimetry Staff (6) (3) (2)
Health Physics Technicians~
HP Staff Advisor (6)
(16)
Laborers (1~)
Temporary (6)
Contract Technicians (6)
Radiation Protection Annunciator 42a - October 1998 WNP-2 Contamination Events - CY98 n
2BB 239.
n F.
0
~FYPERFORMANCE 12
~NON OUTAGE I
a
~
1 30'0 C3
~R
+ II 13 -o El m El 8
CUMMULATIVETOTAL op cf 8
ESTIMATE 0
STATION GOALS: 100 per Non-Outage months: ". per Non-Outage month average
-and- I per Outage.
= 100 Non-Outage - and - 170 Outage (thru July - 98)
PERFORMANCE
SUMMARY
- 270 total contamination events
~ REMARKS: 8 contamination events for October is below monthly goal (10). Breakdown - Month: 8(: i = '), Non-Outage 100 (WHITE), Outage 170- (RED)
Information PcovKIed b . K S ero SATISFACTORY NEEDSIMPROVEMENT ADVERSE POSITIVE WHITE YELLOW
>100 or >10 per month < 105 or <15 per month
Radiation Protection Self Assessments
' (;i+A' V' ~ w<<" a - - i ~. wW e-r n ~
~~~CTtl~
'ygQg p% ~ c . ~ .q ~ ~ v ~ r
~
Recent Self Assessments
)) Effectiveness of Dose Reduction
)) External Dosimetry
)> Control of Radioactive Material
>) Shop Productivity
>) Contamination Control HP Training Respiratory ALARA Assist Visit
)> Effectiveness of Post Job Reviews (Dec)
RP Program Annual (Dec)
~
~ ~
Radiation Protection Summary and Challenges
~ < If
~ Contamination Control
~ Exposure Reduction
~ Safety Culture
Engineering John A. McDonald Engineering General Manager
1997 PSA Summary
~ Average performance iimprovedJ
~ Fewer overdue PTL
~ Reduction in backlog
~ Improved plant support
- I Improved work quality *
~ Good equipment performance "
~ Improved training and qualification
- 96 F'SA Observation
~ Turnover process *
~ Retention of design basis knowledge
~ Work product inconsistency *
~ Large backlogs *
~ Process inefficiencies
~ Emergent work
~ System performance monitoring
- 96 F'SA Observation
PSA ISSUES
~~~Q+p~5@~+~ i&~<. iR'&ixk AS~"Zl""> Ij)A~j~~T- Ki+~,l~+~ ~i~~"f~:!~~. ills, <>fQn~z~.;"': ~ ~-~i '~ '..:~a'~,2~=:-..f~~,".:, ', . -::, ',.
. ~ . e! P..+ .>>-.3~.
0 o~. go go
~o o Engineering Business Leadershi Resource Mana ement X X X Corrective Action Plan X X System Performance X X Project Implementation . X Desi n DataBase X
'H Business Plan Inputs
~ Self Assessments
~ NRC
~ INPO
~ QA
. o Site initiatives
Self Assessments Performed
~ Calculations (10/97)
~ Field Change Requests (10/97(
~ System Performance Monitoring (1/98) e Configuration Control (1/98)
~ Use of Generic Guidance in 50.59 (3/9SJ
~ ECCS Strainer (3/98) e Severe Accident Management (6/98) o Fuel Vendor (6/98]
Self Assessments Performed
~ Y2K (7/98)
~ Core Reload Design (9/98)
~ INPO Assist on Equipment Performance Monitoring (9/98)
~ Engineering Business Plan (10/98) e Post Fire Safe Shutdown Methodology (1 1/98 )
o Option Finder Questionnaire (1 1/98) o Project Lessons Learned (Monthly
Self Assessment Areas For Improvement System performance monitoring data familiarity Project implementation Backlog reduction progress FCR processing issues
~ Too many design data bases Lack of formal calculation checkout Cumbersome calculation control procedure Large number of CMRs
Self Assessment Areas For Improvement
~>~~~CD~~'<~~g~~~; P'.~+PPQ~>~~~~~i.. r~lP~C'7~+.>%~i.~~i<<rQ~W~~a~W~~)~e,M~~+~irg<<'~%~>5>!%5+.~ M'P'~<g "A~ ~ ' .: "y:. g, w . ~ ~- ~ ">>, i,,+~w*'a~~p- r)
~ inadequate calculation procedure for interfacing calculation impacts
~ Cumbersome design data retrievability
~ Up-to-date Reactor Engineer qualifications
~ Resource management
~ No core reload project schedule o Y2K contingency planning
~ Complicated configuration control process
~ Lack of detailed ECCS strainer project schedule
Self Assessment Schedule PDIS Rev 0 Installation (Feb 99)
Reactor Engineering Processes & Procedures (May 99)
Equipment Performance (Jun 99)
Software Control & Change Process (July 99(
Adequacy, Knowledge, & Retrieval of Design Bases (July 99)
Thermolag (Oct 99)
Maintenance Rule (Oct 99)
Field Change Request (Dec 99)
FPFI Assessment (Jan OOJ
- ,"r~'" r"-'=".-"rr..
- -'-.=".:i'.=:r. "-'-">"'- "="'N V C L E A R=..S A F E T Y e
A ARA OER BAC OG Q A FICAT 0 MGMT r r r r r 112% 96% '4 t 5-'<. '<<;$
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~ex-~rrz Qg++i+ lirgr 0.59 ERRORS AO R ORS C s r r 4
r r 2 6 ours ee T 0 ER
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6.5% 14.8%
7.4%
O.S')T,:C 0 M'. E.T iT IVE N E:S S GR B DG T B C OG OG 0 1 R.
r r 9.1%
j '
',(1Y2'> 'ys G G Cl R AC OG PMRs OT C OS r r r r 1568 12 1 2 No'oa ta r
1074 26 M ATE RIAL.,C0ND ITION 0 ARO DS S ST AT S r r r 4IQIr'g>>.+. "H3~f<w; rfg9.6 5.~pi r r 15 8
SYSTEM EAC tt'c tt' ttcW P& r
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CRD c ttt< r
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>+i ~ 44~.
NPCS t, <<hatt r 5TNC~MCQ NM R C IC 0!1 DEN <<'t rtt<<'rrr 1 A~'4c tttN'c RFW
<, s TG ltvt t ~ M vttcr, e+bU~.WA W%
COND <<gal',+ << ttt vt 0 pfp~t,y3 r RPS TSW tAvtv t,vl t>>
't'g If QgWiC GAS c C V8 IC E P N S ~
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" <<A."~4 P'>f' 0 G t tI't6~ 9 4gP ~k ".,>~ty'g0v'!0 SCW t,c,'t w tta a
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RRC tt t c
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Human Performance FgfK+~~a~'">=~~'-~c .:zs~-j"~c'vc:ca~ ~iji"fi44~6@~~vM~4~~~>3iÃ~
3.00 Cl Monthly Error Rate LLI -
Least Squares Fit of Monthly Data
< 250 I
+~ 2.00 0
x 3.50 CI IX
'Ll 1.00 Q.
(0
~ 050 ul 0.00 CO Co CO r t co 00 co CD CD CD CD CD <<D CD CD CD CD CD CD I
O O CD D
0 Q o o D
6 Engineering Backlog pp~+w:)p>g~Irg~p p vOi0 0 0"<
2000 1500 II O
)L III
~ I 000 X
SI 500 0
a IE BACKLOG BY DRIVING DOCUMENT TYP E 140 120 1OO I-
- u. 80 IP'P 0
60 4o )~g)
R 20
" (jI'lg kt:
<t'.
0 0O O O
0 0
Calculations with more than 5 CMRs
<~~gW~~r>> %&+5+~'Ig .~5~.K i- ~~ <',-'5IY~e../ >>Jx~g:%~>>~I>> 1'&iH. >>~T ~~V~. ~ 1>',. g~t,"r w . ~, .- '. ~ ', ~ . '-t ~
70 60 50 c
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1 r' 2, I' 5 5
I
- 1 10 5
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Major Scheduled Actions
[PTL]
o Quality of Work Expectations [12/98)
~ Engineering Work Management System (12/98 J
~ Project Implementation (1/99(
~ Backlog Evaluation (1/99)
~ System Performance Monitoring (4/99(
~ Consolidate Problem Identification Methods (6/99) o Design Data Base (2/OOJ
Engineering Successes I K'th4~~, Q~vggvYleg gP~P g)<IP gAg8 )t' 'P~~PN > <X Irgj<> PplQ~
and Challen es
~ . ~y ', '~q'>>>: aP'hA~C Al~a /j)vr)w rC>nPgx ~ 'gg.'q, w" .- g 'wg'. ' ' '
Current Successes
~ Project Coritrols o Corrective Action Program o Self Assessment o Business Plan Current Challenges o System Performance Monitoring o Design Data Base e Leadership Development
Corrective Action Prograrri Cheryl M. Whitcomb Assistant to the Plant General Manager
Improvement Initiative
~ 1SCPPRQP~
o PSA identified need for program improvements primarily related to problem identification and correction
>> Timeliness of PER dispositions and corrective actions
>> Identification of repeat occurrences
>> Quality of root cause analysis
>> Identification of problems on Gold Cards rather than PERs
Improvement Initiative
~ Strategic plan established to identify and implement improvements focused on
>> problem identification and correction
>> program responsibilities
>> program indicators
Problem Identification PQPd~'AQ~Pv and Correction Im rovements
~fgl]h~~g~+QWf~>~+~~gF'~B~~Peri?. $$ F~~):P$ 4gQYj~ra~+~AgT+w~- ~ 4L>((+..P4~;+<Q~~Q'HQ ICQVrr." "l>l"~jy"Z~QPzM~'.seta O~W.Pi i'~h.r,".,,gc.' ' ~ ~, .'. ,, P+r yw 'ail' ~k ' ';
~ Process enhancements (completed/in-progress)
>> PER initiation criteria eliminated process used to identify and correct all problems
>> PER initiated by the individual who identifies the problem
>> Review of Gold Cards enhanced to ensure PERs are initiated for PER related issues
Number of PERs per Month 286 275 228 ~ 228 225 203 175 139 137 125 17 86 75 66
,73 25 Mar Apr May Jun Jul Aug Sep Oct Nov Dec
~
Jan Feb 1997 1998 ytd
Problem Identification and Correction Improvements
>> Quick disposition of less significant problems at time of initiation
>> Corrective actions focused on fixing the problem
>> Modified significant PER criteria
Problem Identification and Correction Improvements
~ Trending enhancements (in-progress)
>> Identification of repeat occurrences, adverse trends, local/global issues enhanced by better characterization of what and why the problem occurred performance of a common cause analysis on a periodic basis
~ Program procedures more user friendly (in-progress}
Program Responsibilities
~ Program roles and responsibilities revisited to ensure understanding and accountability {completed)
Program Indicators
~ Current indicators enhanced {completed}
>> Timeliness of corrective actions
~ New indicators established, focused on problem identification and correction (in-prog ress}
>> Repeat and significant problem rate
>> Number of self-identified conditions
>> Root cause analysis quality