Package Containing Attachment to Employee Concerns ProgramsML20058P093 |
Person / Time |
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Site: |
Peach Bottom ![Constellation icon.png](/w/images/b/be/Constellation_icon.png) |
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Issue date: |
09/17/1993 |
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From: |
Stephen Baker NRC |
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To: |
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References |
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NUDOCS 9312230057 |
Download: ML20058P093 (5) |
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Category:ARCHIVE RECORDS
MONTHYEARML20210A4951999-07-22022 July 1999 Package Consisting of Questions & Comments Re PBAPS Submittal,Dtd 980813,in Support of Discussion on Listed Items ML20151X8811998-06-23023 June 1998 Rev 2 to PM-1011, Core Spray Pump Npsh ML20151X8721998-06-23023 June 1998 Rev 2 to PM-1010, RHR Pump Npsh ML20151X8621998-06-22022 June 1998 Rev 1 to PM-1013, Min Containment Pressure Available ML20195E3151998-04-27027 April 1998 Non-proprietary Version of Rev 1 to Calculation MISC-PENG- CALC-064, Verification of ECCS Strainer Pressure Drops for Peach Bottom,Units 2 & 3 ML20195E3551997-11-28028 November 1997 Non-proprietary Version of Rev 1 to Calculation MISC-PENG- CALC-062, Evaluation of Predictions & Data for Prototype Strainer ML20216E6891997-08-0404 August 1997 Calculation 0067-000-84-C-020 (PS-0920), Clipped A-46 Spectra for Radwaste/Turbine Building. W/14 Oversize Drawings ML20216E7491997-07-24024 July 1997 Calculation CTLAR-01 PS-0939, LAR of Raceway Supports for PBAPS Units 2 & 3 ML20216E7161997-04-28028 April 1997 Calculation 0067-00084-C-011 PS-0912, LAR of Raceways ML20134D5471996-10-28028 October 1996 Press Release I-96-71, Parts of Local PDR for Three Mile Island & Peach Bottom Nuclear Plants Reopened ML20058P0931993-09-17017 September 1993 Package Containing Attachment to Employee Concerns Programs ML20086C4921991-10-0404 October 1991 Design of Full Structural Weld Overlay on Pbaps,Unit 3 Reactor Water Cleanup Weld No 12-I-1C ML20247H9431989-07-25025 July 1989 Summary of ASME Repairs & Replacement Completed (N1S-2) for Peach Bottom Atomic Power Station Unit 2,870401-890426 ML20237D7901987-12-10010 December 1987 Package of Unrelated Documentation Re Listed Plants Concerning NRC Emergency Response Data Sys IA-87-759, Annotated Slides of NRC 870909 Briefing on Pipe Replacement Project1987-09-0909 September 1987 Annotated Slides of NRC 870909 Briefing on Pipe Replacement Project ML20236X0061987-09-0909 September 1987 Annotated Slides of NRC 870909 Briefing on Pipe Replacement Project IA-87-209, Package of Undated Documents Re NRC Briefing of Commission Concerning Shutdown of Plant1987-07-23023 July 1987 Package of Undated Documents Re NRC Briefing of Commission Concerning Shutdown of Plant ML20235Y5381987-07-23023 July 1987 Package of Undated Documents Re NRC Briefing of Commission Concerning Shutdown of Plant ML20151M9601987-07-20020 July 1987 Package of NRC Administered Requalification Exam Results Summary ML20235N6621987-07-15015 July 1987 Package of Partially Withheld Investigation Status Records, Draft Synopsis,Handwritten Notes & Util Personnel Policy Re Case 1-85-019 Concerning Alleged Threats to Employees to Prevent Disclosure of Possible Overexposure to NRC ML20235A1861987-07-0101 July 1987 Partially Withheld Package Consisting of Radiation Work Permit 3-1-003,discrepancy Rept,Radiation Contamination - Airborne Survey & Radiation Work Permit Access & Exposure Control ML20206N8911987-04-14014 April 1987 Revised Viewgraphs to 870410 Transcript on Commission Briefing Re Status of Facility ML20214E4881987-04-0606 April 1987 Press Release Re Util Plan to Investigate Reasons for NRC Order Suspending Plant Operation IA-87-185, Partially Deleted Encl from SECY-86-322 Discussing Declining Performance Trends,Plant SALP for Apr 1985 - Jan 1986 & Enforcement Conference W/Util.Util Seems Responsive Toward Improved Performance1986-10-29029 October 1986 Partially Deleted Encl from SECY-86-322 Discussing Declining Performance Trends,Plant SALP for Apr 1985 - Jan 1986 & Enforcement Conference W/Util.Util Seems Responsive Toward Improved Performance ML20216F4841986-10-29029 October 1986 Partially Deleted Encl from SECY-86-322 Discussing Declining Performance Trends,Plant SALP for Apr 1985 - Jan 1986 & Enforcement Conference W/Util.Util Seems Responsive Toward Improved Performance IA-85-771, Package of Reactor Operator & Senior Reactor Operator Exam Questions & Answer Keys for Personnel at Facilities1986-01-0303 January 1986 Package of Reactor Operator & Senior Reactor Operator Exam Questions & Answer Keys for Personnel at Facilities ML20137Q6671986-01-0303 January 1986 Package of Reactor Operator & Senior Reactor Operator Exam Questions & Answer Keys for Personnel at Facilities ML20154B8891985-10-0101 October 1985 Slide Presentation Entitled, Performance of L Grade Stainless Steel Recirculation Outlet Safe Ends at Peach Bottom-3. List of Attendees Encl ML20129F4831985-05-0909 May 1985 Package of Compilations of Results of Operator Licensing & Requalification Exams 1999-07-22
[Table view] Category:PACKAGE OF NONCODED MATERIAL
MONTHYEARML20210A4951999-07-22022 July 1999 Package Consisting of Questions & Comments Re PBAPS Submittal,Dtd 980813,in Support of Discussion on Listed Items ML20058P0931993-09-17017 September 1993 Package Containing Attachment to Employee Concerns Programs ML20247H9431989-07-25025 July 1989 Summary of ASME Repairs & Replacement Completed (N1S-2) for Peach Bottom Atomic Power Station Unit 2,870401-890426 ML20237D7901987-12-10010 December 1987 Package of Unrelated Documentation Re Listed Plants Concerning NRC Emergency Response Data Sys IA-87-209, Package of Undated Documents Re NRC Briefing of Commission Concerning Shutdown of Plant1987-07-23023 July 1987 Package of Undated Documents Re NRC Briefing of Commission Concerning Shutdown of Plant ML20235Y5381987-07-23023 July 1987 Package of Undated Documents Re NRC Briefing of Commission Concerning Shutdown of Plant ML20151M9601987-07-20020 July 1987 Package of NRC Administered Requalification Exam Results Summary ML20235N6621987-07-15015 July 1987 Package of Partially Withheld Investigation Status Records, Draft Synopsis,Handwritten Notes & Util Personnel Policy Re Case 1-85-019 Concerning Alleged Threats to Employees to Prevent Disclosure of Possible Overexposure to NRC ML20235A1861987-07-0101 July 1987 Partially Withheld Package Consisting of Radiation Work Permit 3-1-003,discrepancy Rept,Radiation Contamination - Airborne Survey & Radiation Work Permit Access & Exposure Control IA-87-185, Partially Deleted Encl from SECY-86-322 Discussing Declining Performance Trends,Plant SALP for Apr 1985 - Jan 1986 & Enforcement Conference W/Util.Util Seems Responsive Toward Improved Performance1986-10-29029 October 1986 Partially Deleted Encl from SECY-86-322 Discussing Declining Performance Trends,Plant SALP for Apr 1985 - Jan 1986 & Enforcement Conference W/Util.Util Seems Responsive Toward Improved Performance ML20216F4841986-10-29029 October 1986 Partially Deleted Encl from SECY-86-322 Discussing Declining Performance Trends,Plant SALP for Apr 1985 - Jan 1986 & Enforcement Conference W/Util.Util Seems Responsive Toward Improved Performance ML20137Q6671986-01-0303 January 1986 Package of Reactor Operator & Senior Reactor Operator Exam Questions & Answer Keys for Personnel at Facilities IA-85-771, Package of Reactor Operator & Senior Reactor Operator Exam Questions & Answer Keys for Personnel at Facilities1986-01-0303 January 1986 Package of Reactor Operator & Senior Reactor Operator Exam Questions & Answer Keys for Personnel at Facilities ML20129F4831985-05-0909 May 1985 Package of Compilations of Results of Operator Licensing & Requalification Exams 1999-07-22
[Table view] |
Text
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TI 2500/028 - Attachment EMPLOYEE CONCERNS PROGRAMS PLANT NAME: Peach Bottom 2 & 3 LICENSEE: Philadelphia Electric Co. (PECo)
DOCKET #: 50-277 & 50-278 NOTE: Please indicate yes or no, if applicable, and add comments in the space provided.
A. PROGRAM:
- 1. Does the licensee have an employee concerns program?
Yes Comments:
There are two proceduralized programs and one informal program in effect:
A-C-905. Ouality Concerns & A11ecations, applies to all PECo employees and contract personnel associated with the nuclear group.
NOA-29. Ouality Exit Interviews, applies to all technical PECo and contracted Nuclear Quality Assurance (NQA) personnel.
Quality Exit Interview form similar to that in NQA-29 was developed by the Human Resources (personnel) department to be used for all nuclear group personnel when completing assignment within the nuclear group.
- 2. Has NRC inspected the program? No Comments: Results of this inspection will be documented in inspection report 93-17.
B. SCOPE:
- 1. Is it for:
- a. Technical? Yes
- b. Administrative? Yes
- c. Personnel issues? Yes
- 2. Does it cover safety as well as non-safety issues? Yes comments: All three ECP programs were designed for safety issues, but they allow for reporting of reporting of non-safety issues as well. Additionally, they can be used for suggestions to improve the operations within the nuclear group.
- 3. Is it designed for:
- a. Nuclear safety? Yes
- b. Personal safety? Yes
- c. Personnel issues - including union grievances? Yes
- 4. Does the program apply to all licensee employees? Yes Comments: See elaboration above in section A.l.
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- 5. Does the program apply to contractors? Yes
- 6. Does the licensee require its contractors and their subs to have a similar program? No
- 7. Does the licensee conduct an exit interview upon terminating employees asking if they have any safety concerns? Yes i comments: As explained, all NQA personnel are required to receive an exit interview. However, there is no requirement for any other personnel to be interviewed upon termination.
C. INDEPENDENCE:
- 1. What is the title of the person in charge?
Director, Nuclear Quality Assurance
- 2. Who do they report to?
formal - Senior Vice President,. Nuclear information only - President of the Company and Nuclear Committee of the Board
- 3. Are they independent of line management? Yes
- 4. Does the ECP use third party consultants?
Not routinely. On the one occasion that the quality concern involved the NQA organization, an outside consultant was utilized. Sometimes other groups within the PECo organization will be asked to support an investigation..
- 5. How is a concern about a manager or vice president followed up?
No differently than any other concern.
D. RESOURCES:
- 1. What is the size of the staff devoted to this program?
There is no formal group designated for the ECP. The Director, NQA, is responsible for the implementation of the program. A pool of interviewers and investigators is available to the Director, NQA. This ' pool includes QA ,
inspectors, the Independent Safety Engineering Group, Engineering, Corporate Security, and vendor representatives.
- 2. What are ECP staff qualifications (technical training, interviewing training, investigator training,'other)?
There are no formal requirements. Selection of individuals is based on experience, personnel background, and the specific issue.
E. REFERRALS:
- 1. Who has followup on concerns (ECP staff, line management, other)?
The Director, NQA, is responsible for ensuring all concerns A-2
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F. CONFIDENTIALITY:
- 1. Are the reports confidential? Yes 2.- Who is the identity of the alleger made known to (senior !
management, ECP staff, line management, other)?
The Director, NQA, and his secretary are the only ones who have access to the alleger's identity.
- 3. Can employees be:
- a. ' Anonymous? Yes
- b. Report by phone? Yes G. FEEDBACK:
- 1. Is feedback given to the alleger upon completion of the followup? Yes comments: normally, the alleger is contacted by telephone at home, followed by a registered letter with the details of the investigation
- 2. Does program reward good ideas? Yes comments: Suggestions are encouraged. If adopted, the '
employee can pursue a financial award.
- 3. Who, or at what level, makes the final decision of resolution? l Director, NQA [
- 4. Are the resolutions of anonymous concerns disseminated? .;
No
- 5. Are the -resolutions of valid concerns publicized (newsletter, bulletin board, all hands meeting, other)?
No l
H. EFFECTIVENESS:
- l. How does the licensee measure the effectiveness of the !
program? j Comments: the licensee does not measure directly program i effectiveness. However, Director, NQA, indicated that he felt the program was effective based on low utilization, !
issues were readily resolved, and no generic implications had been identified.
- 2. Are concerns:
- a. Trended? Not presently, but intends to start this yesr.
- b. Used? No
- 3. In the last three years how many concerns were raised? ,
23 l i
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Of;the concerns raised,;howLuany were closed?- ,
20 !
What-percentage ~were substantiated? 65% < l What percentage of substantiated _ were quality concerns? q 60%
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- 4. How are' followup techniques used to measure effectiveness (random survey, interviews. other)? d Comment: Effectiveness is not measured.
- 5. How frequently are internal audits of the ECP' conducted _ ,
and by whom? i Never ~I
.I. ADMINISTRATIVE / TRAINING:
- 1. Is ECP_ prescribed by a procedure? f Yes i
- 2. How are employees, as well as contractors, made~ aware of ~!
this program (training, newsletter, bulletin board, other)? .
Comment: during the initial general employee training (GET). i and annual GET refresher training '
ADDITIONAL COMMENTS: '
(Including characteristics which make the program .especially ?
effective, if any). !
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t NAME: TITLE: PHONE #: DATE COMPLETED: i B. S. Norris Senior Resident Inspector 717/456-7614- [
August 25. 1993
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-t From: Sherri L. Baker (SLB1)
-To: RPR Date: Friday, September 17, 1993 1:15 pm
Subject:
PBAPS APPENDIX A RICHARD, ;
ATTACHED IS THE PEACH BOTTOM 2 & 3 APPENDIX A FOR YOUR REVIEW.
IF YOU HAVE ANY QUESTIONS, PLEASE FEEL FREE TO CONTACT US AT 717-456-7614. -
SHERRI BAKER (OA)
CC: RLF1 Files: P:\2500-028.ATT i
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