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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARB17848, Startup Test Rept Cycle 7. with1999-09-30030 September 1999 Startup Test Rept Cycle 7. with ML20211Q3361999-09-0707 September 1999 Proposed Tech Specs Removing Current Special Exception Which Precludes Applying Eighteen Month Functional Testing Surveillance to SG Hydraulic Snubbers ML20211H6471999-08-25025 August 1999 Proposed Defueled Tech Specs,Revising Sections 5.6.1,5.7.2 & 5.7.3 & Adding Proposed Section 5.6.4 to Reflect ACs Contained in NUREG-1433 ML20210Q5211999-08-0505 August 1999 Proposed Tech Specs Sections 3.8.3.2,4.6.2.1,4.6.2.2, 4.8.1.1,4.9.12 & Bases Section B 3/4.3.2,B 3/4.6.1.2 & B 3/4.8.4,incorporating Editorial Revs ML20210C6091999-07-16016 July 1999 Proposed Tech Specs Relocating Selected TS Related to Refueling Operations & Associated Bases to Plant TRM ML20206U1041999-05-17017 May 1999 Proposed Tech Specs Section 4.4.6.2.2.e,deleting Reference to ASME Code Paragraph IWV-3472(b) Re Frequency of Leakage Rate Testing for Valves Six Inches Nominal Pipe Size & Larger ML20206M8221999-05-10010 May 1999 Restart Assessment Plan Millstone Station ML20206D1761999-04-27027 April 1999 Rev 1 to Millstone Unit 3 ISI Program Manual,Second Ten-Yr Interval ML20205R2411999-04-19019 April 1999 Rev 3 to CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205R2501999-04-19019 April 1999 Rev 0 to CP2804M, Unit 2 Vent & Containment Air Pass ML20205R2751999-04-19019 April 1999 Proposed Tech Specs,Reflecting Permanently Defueled Condition of Unit ML20205S5611999-04-16016 April 1999 Rev 5 to Epop 4426, On-Site Emergency Radiological Surveys ML20205M0891999-04-0707 April 1999 Proposed Tech Specs Modifying Value for Monthly Surveillance Testing of Tdafwp ML20205E4411999-03-29029 March 1999 Rev 2 to CP 2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20196K5771999-03-24024 March 1999 Rev 1 to Chemistry Procedure CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205D5321999-03-22022 March 1999 Rev 3 to RPM 2.3.5, Insp & Inventory of Respiratory Protection Equipment ML20204J1581999-03-19019 March 1999 Proposed Tech Specs Section 6, Administrative Controls, Reflecting Certified Fuel Handler License Amend Changes, Approved on 990305 ML20204J4101999-03-19019 March 1999 Proposed Tech Specs Relocating Instrumentation TSs 3.3.3.2, 3.3.3.3 & 3.3.3.4 to Mnps,Unit 2 TRM ML20204K0971999-03-19019 March 1999 Proposed Tech Specs Supporting Spent Fuel Pool Rerack to Maintain Full Core Reserve Capability Approaching End of OL ML20204F9031999-03-17017 March 1999 Proposed Tech Specs,Revising 3.5.2,3.7.1.7 & 3.7.6.1 Re ECCS Valves,Atmospheric Steam Dump Valves & CR Ventilation Sys. Associated Bases Will Be Modified as Necessary to Address Proposed Changes ML20207H9551999-03-0505 March 1999 Proposed Tech Specs Section 6.0 Re Administrative Controls ML20206K1121999-03-0505 March 1999 Proposed Tech Specs Bases Sections 3/4.7.7, CR Emergency Ventilation Sys & 3/4.7.8 CR Envelope Pressurization Sys. Changes Are Editorial in Nature ML20207F6211999-03-0303 March 1999 Rev 2,change 1 to Communications - Radiopaging & Callback Monthly Operability Test ML20207E0321999-03-0202 March 1999 Proposed Tech Specs 3/4.7.4, SW Sys, Proposing Change by Adding AOT for One SW Pump Using Duration More Line with Significance Associated with Function of Pump ML20207D4821999-02-26026 February 1999 Proposed Tech Specs Re Addl Mods Concerning Compliance Issues Number 4 ML20207J0001999-02-22022 February 1999 Rev 7 to Millstone Unit 2,IST Program for Pumps & Valves ML20206D1991999-02-11011 February 1999 Change 7 to Rev 5 to ISI-3.0, Inservice Testing Program. Pages 2 of 3 & 3 of 3 in Valve Relief Request Section 6.1 of Incoming Submittal Not Included ML20203E4051999-02-11011 February 1999 Proposed Tech Specs Re DG Surveillance Requirements ML20210D2121999-01-21021 January 1999 Proposed Tech Specs Sections 3/4.5.2 & 3/4.5.3, ECCS Subsystems for Info Only ML20199L2841999-01-20020 January 1999 Proposed Tech Specs & Final SAR Proposed Rev to Ms Line Break Analysis & Revised Radiological Consequences of Various Design Basis Accidents ML20199L0801999-01-18018 January 1999 Proposed Tech Specs Change to TS 3/4.2.2 Modifies TS to Be IAW NRC Approved W Methodologies for Heat Flux Hot Channel factor-FQ(Z).Changes to TS Section 6.9.1.6 Are Adminstrative in Nature ML20199L4561999-01-18018 January 1999 Proposed Tech Specs Revising TS Table 3.7-6, Air Temp Monitoring. Proposed FSAR Pages Describing Full Core off- Load Condition as Normal Evolution Under Unit 3 Licensing Basis,Included ML20199L3271999-01-18018 January 1999 Proposed Tech Specs 3.6.1.2, Containment Sys - Containment Leakage ML20199L0431999-01-18018 January 1999 Proposed Tech Specs Removing TS 3/4.6.4.3, Containment Systems,Hydrogen Purge Sys ML20199E0931999-01-13013 January 1999 Rev 2 to Health Physics Support Procedure RPM 2.3.4, Insp & Maint Process for Respiratory Protection Equipment ML20206P5121999-01-0404 January 1999 Proposed Tech Specs 3.5.2,3.6.2.1,3.7.1.2,3.7.3.1 & 3.7.4.1, Incorporating Changes to ESF Pump Testing B17501, 1998 - 2000 Performance Plan - Work Environ Focus Area Update1998-12-31031 December 1998 1998 - 2000 Performance Plan - Work Environ Focus Area Update ML20198K6361998-12-31031 December 1998 Proposed Tech Specs Section 6.0, Administrative Controls ML20199A7531998-12-31031 December 1998 Restart Backlog Mgt Plan Commitments ML20198P9751998-12-28028 December 1998 Proposed Tech Specs Pages Revising Loss of Normal Feedwater (Lonf) Analyses to TS 2.2.1,TS Bases Change to Floor Value for Thermal Margin Low Pressure Reactor Trip & Proposed FSAR Changes ML20196H6301998-12-0404 December 1998 Proposed Tech Specs Re Section 6.0, Administrative Controls ML20197G9831998-12-0404 December 1998 Proposed Tech Specs 4.7.10.e,eliminating Need to Cycle Plant & Components Through SD-startup Cycle by Allowing Next Snubber Surveillance Interval to Be Deferred Until End of RFO6 of 990910,whichever Date Is Earlier ML20196A2181998-11-20020 November 1998 Restart Assessment Plan Millstone Station ML20195D4041998-11-10010 November 1998 Proposed Tech Specs,Modifying Sections 3.3.1.1 & 3.3.2.1 by Restricting Time That Reactor Protection or ESF Actuation Channel Can Be in Bypass Position to 48 H,From Indefinite Period of Time ML20195D8101998-11-10010 November 1998 Revised marked-up Page of Current TS 3.8.1.1 & Revised Retyped Page Re 980717 Request to Change TS ML20195H8681998-11-0404 November 1998 Rev 4 to Millstone Unit 2 Operational Readiness Plan ML20196H5921998-10-29029 October 1998 Rev 0 to TPD-7.088, Millstone 1 Certified Fuel Handler/ Equipment Operator Continuing Training Program ML20196H5861998-10-29029 October 1998 Rev 0 to TPD-7.087, Millstone 1 Certified Fuel Handler Training Program B17548, Rev 0 to TPD-7.089, Millstone 1 Equipment Operator Training Program1998-10-29029 October 1998 Rev 0 to TPD-7.089, Millstone 1 Equipment Operator Training Program ML20155B0331998-10-22022 October 1998 Proposed Tech Specs Changing TS 3.3.2.1, Instrumentation - ESFAS Instrumentation, 3.4.9.3, RCS - Overpressure Protection Sys & ECCS - ECCS Subsystems - Tavg 300 F 1999-09-07
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20206M8221999-05-10010 May 1999 Restart Assessment Plan Millstone Station ML20206D1761999-04-27027 April 1999 Rev 1 to Millstone Unit 3 ISI Program Manual,Second Ten-Yr Interval ML20205R2501999-04-19019 April 1999 Rev 0 to CP2804M, Unit 2 Vent & Containment Air Pass ML20205R2411999-04-19019 April 1999 Rev 3 to CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205S5611999-04-16016 April 1999 Rev 5 to Epop 4426, On-Site Emergency Radiological Surveys ML20205E4411999-03-29029 March 1999 Rev 2 to CP 2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20196K5771999-03-24024 March 1999 Rev 1 to Chemistry Procedure CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205D5321999-03-22022 March 1999 Rev 3 to RPM 2.3.5, Insp & Inventory of Respiratory Protection Equipment ML20207F6211999-03-0303 March 1999 Rev 2,change 1 to Communications - Radiopaging & Callback Monthly Operability Test ML20207J0001999-02-22022 February 1999 Rev 7 to Millstone Unit 2,IST Program for Pumps & Valves ML20206D1991999-02-11011 February 1999 Change 7 to Rev 5 to ISI-3.0, Inservice Testing Program. Pages 2 of 3 & 3 of 3 in Valve Relief Request Section 6.1 of Incoming Submittal Not Included ML20199E0931999-01-13013 January 1999 Rev 2 to Health Physics Support Procedure RPM 2.3.4, Insp & Maint Process for Respiratory Protection Equipment B17501, 1998 - 2000 Performance Plan - Work Environ Focus Area Update1998-12-31031 December 1998 1998 - 2000 Performance Plan - Work Environ Focus Area Update ML20199A7531998-12-31031 December 1998 Restart Backlog Mgt Plan Commitments ML20196A2181998-11-20020 November 1998 Restart Assessment Plan Millstone Station ML20195H8681998-11-0404 November 1998 Rev 4 to Millstone Unit 2 Operational Readiness Plan ML20196H5921998-10-29029 October 1998 Rev 0 to TPD-7.088, Millstone 1 Certified Fuel Handler/ Equipment Operator Continuing Training Program B17548, Rev 0 to TPD-7.089, Millstone 1 Equipment Operator Training Program1998-10-29029 October 1998 Rev 0 to TPD-7.089, Millstone 1 Equipment Operator Training Program ML20196H5861998-10-29029 October 1998 Rev 0 to TPD-7.087, Millstone 1 Certified Fuel Handler Training Program ML20154G5311998-10-0707 October 1998 Rev 4 to Project Procedure PP-02, Accident Mitigation Sys Review ML20154G5391998-10-0606 October 1998 Rev 6 to Project Procedure PP-07, Discrepancy Repts ML20154G5351998-10-0606 October 1998 Rev 3 to Project Procedure PP-04, Regulatory Review Procedure ML20154G5521998-10-0606 October 1998 Rev 5 to Project Instruction PI-01, Svsr Implementation Checklists & Workbook ML20154G5251998-10-0505 October 1998 Rev 4 to Independent C/A Verification Program for Millstone Unit 2 Audit Plan ML20236Q9341998-06-30030 June 1998 Rev 4 to PI-01, Sys Vertical Slice Review Implementation Checklists & Workbook ML20236Q9321998-06-25025 June 1998 Rev 4 to PP-01, Sys Vertical Slice Review ML20153C6171998-06-18018 June 1998 Rev 2 to CP 3804K, PASS Rcs/Rss Sample ML20153C6221998-06-18018 June 1998 Rev 1 to CP 3804L, PASS Containment Air Sample ML20153C6291998-05-31031 May 1998 Rev 0,Change 1 to CP 3804M, PASS Ventilation Samples ML20247R7851998-05-20020 May 1998 Rev 1 to Epop 4455C, Technical Assistant ML20247Q7011998-05-20020 May 1998 Rev 1 to Epop 4490, Implementation of Recovery Operations ML20247R8081998-05-20020 May 1998 Rev 1 to Epop 4455F, Rumor & Inquiry Control ML20247Q6671998-05-20020 May 1998 Rev 1 to Epop 4422A, Thermal Hydraulic Evaluation Methods ML20247Q6901998-05-20020 May 1998 Rev 1 to Epop 4475A, External Resources Coordinator ML20247R7921998-05-20020 May 1998 Rev 1 to Epop 4455D, News Releases ML20247Q6771998-05-20020 May 1998 Rev 1 to Epop 4428I, Direction of Posl Field Sampling ML20247R7541998-05-20020 May 1998 Rev 1 to Epop 4455A, Nuclear News Manager ML20247R7491998-05-20020 May 1998 Rev 1 to Epop 4455, Manager of Public Info ML20216B1791998-05-0808 May 1998 Independent Corrective Action Verification Program for Millstone Unit 3,Interim Rept,Executive Summary ML20247H4581998-04-0909 April 1998 Rev 19 to EOP 35 E-0, Reactor Trip or Safety Injection B17159, Backlog Mgt Plan for Unit 31998-03-31031 March 1998 Backlog Mgt Plan for Unit 3 ML20216K0641998-03-20020 March 1998 Rev 2 to Oversight Plan NNECO - Millstone Site Independent Third Party Oversight Program ML20216H7101998-03-13013 March 1998 Independent Corrective Action Verification Program Status Rept ML20216H7191998-03-0303 March 1998 Independent Corrective Action Verification Program Status Rept ML20203F6931998-02-20020 February 1998 Rev 6 to PI-MP3-11, Discrepancy Rept Submittal & Closure ML20203E2131998-02-19019 February 1998 Cancelled Rev 26 to 1-OPS-10.11, Locked Valve List ML20203D4111998-02-18018 February 1998 Revised 1-OM-index Unit 1 Operations Dept OM Index & Rev 2 to OM 3.8, Millstone Unit 1 Operations Manual ML20203F6751998-02-16016 February 1998 Rev 2 to PI-MP3-07, Review of Accident Mitigation Systems ML20203F6601998-02-16016 February 1998 Rev 5 to Audit Plan for Independent Corrective Action Verification Program ML20216H7351998-02-11011 February 1998 Independent Corrective Action Verification Program Status Rept 1999-05-10
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.i Docket No. 50-423 B14652 l
l Attachment 2 Validation Plan for Action Plan 4.4.3 t
r October 1993 9310290134 931021 SC PDR ADDCK-05000423 '4 S G PDR it! !
Rev.0 Page 1 of 5 VALIDATION PLAN FOR ACTION PLAN 4.4.3 Action Plan
Title:
Employee Concerns Program Action Plan Managert David Diedrick Validation Start Date: May 5, 1993 Validation Plan Prepared by: s. i N. 7h Date: Q\vkO 3, tv.i.e.v.n T . t..o. i Validation Plan Concurrence: $[
(Acton M.m M.n. ped
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/ Date: p' .M ,8f' Validation Plan Approved by: . F. C y.6 Dete: sxs/;3 IPD*tMimit1 $pon.o#
Action Plan Scope and Objectives:
Scope:
This Action Plan consolidates the recommendations developed from the findings of the Allegations Root cause Task Group (ARCTG) to ensure a coordinated, proactive, integratsd approach to monitoring the effectiveness of the committed actions. The management initiatives (COC recommendations) associated with the employee concerns issues identified in the ARCTG are not part of this action plan (See Action Series 1.0) . .*
Objectives:
Address each of the following recommendations of the ARCTG.
1.
Increase the resource level available to the NSCP to support a greater field visibility and easier access. Locate personnel at Millstone, Connecticut Yankee and Berlin. (Ref. Recommendation B.3)
- 2. Effectively communicate the program to. assure employee awareness and demonstrate support from all levels of management.- (Re f. Recommendation - 8. 4)
Rev.O Page 2 of 5 P
VALIDATION PLAN FOR ACTION PLAN 4.4.3 Action Plan Scope and Objectives: (cont)
Objectives: (cont)
- 3. Staff the program with volunteers throughout NE&O who can relate to employees in their assigned locations and who will be accepted as employee peers. (Ref. Recommendation B.3 and 8.5)
- 4. Use the following characteristics for personnel selection and orientation. (Ref. Recommendations 8.5 & 8. 7) :
Be strong employee representatives Have strong interpersonal skills Be capable of being frank with management Be known and accepted by employees at all 1evels.
- 5. Evaluate eliminating the NRT from their role in the Nuclear concerns process once the recommendations concerning the NSCP have been successfully implemented. (Ref. Recommendation 8.10)
Validation Criteria Intended Effects of the Action Plan:
1.
To provide greater field visibility (i.e. , employee awareness) and easier access of the NSCP to personnel who want to use the NSCP.
- 2. To assure employee awareness of the NSCP and visibly demonstrate support for the NSCP by all levels of management.
3.
To gain greater employee acceptance of the NSCP by staffing it with volunteers who can relate to the i
employees.
- 4. To select personnel running the NSCP (i.e.,
{
management and peer representatives) having the following characteristics:
i
Rev.0' Page 3 of 5 VALIDATION PLAN FOR ACTION PLAN 4.4.3 Validation criteria (cont)
Be strong representatives of (employee) issues.
- Have strong interpersonal skills Be capable of being frank with management Be known and accepted by employees at all levels. '
5.
To evaluate the continued need for the NRT option of the NSCP.
NOTE: Five recommendations of the Allegations Root Cause Task Group (ARCTG) were closed out through actions completed prior to issuing Action Plan 4.4.3. ;
These this recommendations have also been included in '
Validation Plan as Intended Effects as follows:
6.
To structure the program as an employee concerns program and not limited to nuclear safety concerns.
- 7. To design the program to be employee advocate (peer) based.
t
- 8. To have the NSCP report to the Chairman of the !
Board of Trustees, and provide periodic updates on )
overall status and unresolved issues to the entire !
Board. Officer incentives should be based, to a degree, on the success of NSCP.
i j
- 9. To consider expanding the role of' the HPES coordinator to be a field resource and advocate for the NSCP. ,
- 10. To improve the level of employee awareness of the !
NRT by effectively communicating the role of NRT. !
[This Intended Effect has been superseded by !
Intended Effect 2 and 5).
{
Validation Approach: !
The following questions will be asked, on an individual basis, of a selected cross-section of NE&O personnel j directly impacted by the implementation of this Action l Plan. '
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7....
e Rev.O Page 4 of 5 VALIDATION PLAN FOR ACTION PLAN 4.4.3 Validation Approach: (cont)
Objective evidence of the results of implementing this Action Plan may also be obtained through a review of relevant documentation effects, associated with specific Action Plan intended f
la. Are you more aware, just as aware, or less aware of the availability of the NSCP now than in the past?
lb. Is access to the NSCP easier, harder, or no-different now that it was in the past (i . e . , to contact a representative of the NSCP)?
Ic. What is the quarterly trend, from January, 1990 to present, in allegations received by the NRC vs. the NSCP - better, worse, or stayed the same? [ Review data available from the NSCP]
2a. Have communications about the NSCP been given sufficiently wide, too narrow, or too broad enough circulation to effectively inform employees of the existence of the NSCP?
2b. Does your management demonstrate active, passive, or no support of the NSCP?
3a. If you have a complaint, who would you go to get it resolved?
3b. Is this the same answer you would have given about 2 years ago? If not, who would have you contacted?
4a. Based on your knowledge of and contact with NSCP management and peer representatives, do you agree or disagree that these individuals possess the following characteristics as a group?
Are strong representatives of (employee) issues.
Have strong interpersonal skills
- Are capable of being frank with management Are known and accepted by employees at ,
all levels.
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Rev.0 Page 5 of 5 VALIDATION PLAN FOR ACTION PLAN 4.4.3 validation Approach: (cont)
The following questions are to be answered by the Validation Team based on their review of appropriate documents, and observations of the implementation of the NSCP.
Sa. Has the necessity for the NRT role in nuclear concerns been eliminated after the NSCP recommendations were implemented and found to be fully functional?
6a. Has the NSCP been structured as an employee concerns program and not limited to a nuclear safety concerns program?
7a.
Has the NSCP been organized to include employee representatives?
Ba. Does the NSCP report to the Chairman of the Board of Trustees, and provide periodic updates on overall status and unresolved issues to the entire Board?
Bb. Are Officer incentives based, to a degree, on the success of NSCP?
9a.
Has consideration been given to expanding the role of the HPES coordinator to be a field resource and advocate for the NSCP?
Decision Criteria:
The Intended Effects of this Action Plan will have been achieved if the Validation Team finds that the answers to the Validation Approach questions substantiate that the Nuclear Safety Concerns Program has been effectively designed and implemented.
.