ML033350387
| ML033350387 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/01/2003 |
| From: | Grobe J NRC/RGN-III |
| To: | NRC/RGN-III |
| References | |
| IMC 0350 | |
| Download: ML033350387 (21) | |
Text
December 1, 2003 MEMORANDUM TO: Davis-Besse Oversight Panel FROM: John A. Grobe, Chairman, Davis-Besse Oversight Panel /RA/
SUBJECT:
MINUTES OF INTERNAL MEETING OF THE DAVIS-BESSE OVERSIGHT PANEL The implementation of the IMC 0350 process for the Davis-Besse Nuclear Power Station was announced on April 29, 2002. An internal panel meeting was held on October 14, 2003. Attached for your information are the minutes from the internal meeting of the Davis-Besse Oversight Panel, the Open Action Items List, and the closed Restart Action Matrix items.
Attachments: As stated cc w/att: D. Weaver, OEDO J. Caldwell, RIII G. Grant, RIII S. Reynolds, DRP R. Gardner, DRS B. Clayton, EICS G. Wright, DRP DB0350
December 1, 2003 MEMORANDUM TO: Davis-Besse Oversight Panel FROM: John A. Grobe, Chairman, Davis-Besse Oversight Panel /RA/
SUBJECT:
MINUTES OF INTERNAL MEETING OF THE DAVIS-BESSE OVERSIGHT PANEL The implementation of the IMC 0350 process for the Davis-Besse Nuclear Power Station was announced on April 29, 2002. An internal panel meeting was held on October 14, 2003. Attached for your information are the minutes from the internal meeting of the Davis-Besse Oversight Panel, the Open Action Items List, and the closed Restart Action Matrix items.
Attachments: As stated cc w/att: D. Weaver, OEDO J. Caldwell, RIII G. Grant, RIII S. Reynolds, DRP R. Gardner, DRS B. Clayton, EICS G. Wright, DRP DB0350 DOCUMENT NAME: C:\ORPCheckout\FileNET\ML033350387.WPD To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure "N" = No copy OFFICE RIII RIII RIII RIII NAME RBaker/trn DPassehl CLipa JGrobe DATE 11/20/03 11/24/03 11/25/03 12/01/03 OFFICIAL RECORD COPY MEETING MINUTES: Internal IMC 0350 Oversight Panel Meeting
Davis-Besse Nuclear Power Station DATE: October 14, 2003 TIME: 12:30 p.m. Central ATTENDEES:
J. Grobe B. Ruland J. Hopkins C. Lipa A. Mendiola R. Baker D. Passehl J. Stang F. Lyon M. Phillips M. Holmberg Agenda Items:
- 1. Discuss/Approve Todays Agenda The Panel approved the agenda, but modified the order of presentations. THE APPROVED AGENDA REFLECTS THE ORDER LISTED IN THESE MINUTES.
- 2. Discuss Restart Checklist Item 2.d, "Extent-of-Condition of Boric Acid in Systems Outside Containment" Mr. Holmberg presented the Panel with the results from the October 6-10, 2003 review of the licensee resolution of NRC Restart Checklist Item 2.d, Extent-of-Condition of Boric Acid in Systems Outside Containment. Specifically, the inspectors reviewed the licensees closure packages for CH-IAP-2c-02, Containment Health Assurance Implementation Action Plan and SH-DAP-5A-01, System Health Assurance Discovery Action Plan. In accordance with EN-DP-1506, Borated Water System Inspections (Outside Containment), the licensee had performed inspections of each system outside containment that contained borated water using personnel qualified as Mechanical Boric Acid Corrosion Control Inspectors. EN-DP-1506, also specifies that evidence of boric acid residue or corrosion will be documented in a CR. This level of inspection for systems outside containment is required to be performed at 2 year intervals in accordance with the Plant Engineering Program Manual. Although only one of six volumes of the closure package was complete and available, a sample review of the 45 condition reports and associated corrective actions contained in Volume 1 resulted in no findings of significance being identified. THE PANEL APPROVED CLOSURE OF RESTART CHECKLIST ITEM 2.D, "EXTENT-OF-CONDITION OF BORIC ACID IN SYSTEMS OUTSIDE CONTAINMENT."
- 3. Discuss Communication Status Mr. Stang provided an update on the status of the Comm. Plan Matrix covering 0350 issues. The Comm Team review had categorized ~100 of ~125 email messages.
Comm. Plan Matrix open items should be available Thursday (10/16) and the Comm.
Team will brain-storm these issues during their next meeting (Thursday 10/16) and be 1
able to brief the Panel on the following Thursday, 10/23. This should include rules for dispositioning received emails.
- 4. Discuss RAM Closure Forms Mr. Phillips presented the Panel with several RAM items recommended for closure.
One item, L-76, was kept open for revision, and all others were accepted for closure.
THE RESTART ACTION MATRIX ITEMS THAT THE PANEL APPROVED FOR CLOSURE ARE ATTACHED TO THESE MINUTES.
- 5. Discuss Regulatory Footprint Options Mr. Grobe led a discussion on options available for defining the format of the regulatory footprint imposed following restart. The discussion addressed three key areas: 1) Do we need to impose a footprint action; 2) Which type of action is most appropriate; and
- 3) What are the key potential areas of concern.
The Panel was in agreement on the five potential areas of concern discussed, which were:
- Safety Culture and Safety Conscious Work Environment improvement effectiveness;
- Adequacy and improvement of Apparent Cause assessments;
- Continued improvement in the general area of Engineering Calculations;
- Demonstrating effectiveness of the corrective action program Trending Program; and Performing assessment reviews of the effectiveness of corrective actions taken for significant conditions adverse to quality.
- Mr. Grobe next presented the options for available actions, i.e., Confirmatory Action Letter, Confirmatory Order, or License Amendment, and the Panel discussed the pros and cons of each tool.
Following this discussion, the Panel affirmed its intent to utilize a Confirmatory Order to establish post-restart expectations for continuing action and monitoring in important areas.
- 6. Discuss New/Potential Licensing Issues Mr. Stang stated that the licensee is still drafting their Restart letter, and that he had received a question concerning the list of Issues to be resolved for Davis-Besse to restart, (restart criteria) included in the monthly NRC Update newsletters presented at the 0350 public meetings. The Panel will review and discuss these item at the next meeting, 10/16.
- 7. Discuss Punch List Mrs. Lipa discussed the need to define a most reasonable end date for the completion of the list. A date of 12/15/2003 will be earmarked and the leads and milestones will be defined and presented to the Panel next week.
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- 8. Discuss Action Items The Panel reviewed the following open Action Items with comments as noted:
Item 73 (Open) - Send feedback form on IMC 0350 procedure to IIPB. (08/06)
Submittal needs to be coordinated to preclude sending information twice.
Item 138 (Open) - Evaluate the effectiveness of the Comm Plan. (01/07)
The new revised Comm. Plan is with the Panel Chairman for review. This item will be closed upon approval of the revised plan.
Item 147 (Open) - Generate a list of items to consider after restart as well as transition back to the normal 0350 when terminating the 0350 Panel. The items should include plans to augment inspection of corrective actions, inservice inspection, and safety culture monitoring. (01/09)
The inspection schedules and focus areas for post restart are incorporated in the punch list. When developed, the listing for 0350 Panel termination criteria will be presented to the Panel for approval.
Item 178 (Open) - Determine the type of backlog assessment that will be performed and by whom. Two attributes need to be considered: (1) the capability of the licensee to manage the backlog in an operating environment; and (2) the impact of the backlog on equipment reliability. (03/04)
The backlog assessment will be conducted by S. Burgess and M. Parker, starting 11/17/2003. Inspection plan will be presented to the Panel on 10/21/2003.
Item 189 (Closed) - Collect information on the regulatory approach to research the process to ensure proper Regulatory Footprint upon restart. (05/16)
Information used for background data and Panel affirmed which tool to utilize at todays meeting.
The Panel determined that this item is closed.
Item 193 (Open) - Consider TIA on an issue pertaining to 10 CFR 50, Appendix R, Section III-L, "Alternative and Dedicated Shutdown Capability." (05/27)
An update will be presented to the Panel at a future meeting.
Item 196 (Closed) - Determine whether the shift manager is qualified to fulfill the shift engineer position in an emergency and whether there is an adverse impact on the licensee's emergency procedure Implementation. (06/17) Item re-opened at 7/1 Panel meeting.
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The Davis Besse Technical Specification states the following guidance, in regards to control room staffing and minimum shift compliment for operational Modes 1-4:
- 6.2.2.c - At least two licensed operators, one of which has a Senior Reactor Operators license shall be present in the control room while in Modes 1, 2, 3, or 4; and
- 6.2.2.a - Each duty shift shall be comprised of at least the minimum shift crew composition shown in Table 6.2-1.
Per Table 6.2-1, the minimum shift crew composition for Modes 1 - 4, consists of :
- 2 Senior Reactor Operators (SRO)
- 2 Licensed Operators
- 2 Non-Licensed Operators
- 1 Shift Technical Advisor (STA)
The table has guidance that one of the two individuals filling the SRO positions may also assume the STA function provided the individual meets the qualifications for the combined SRO/STA position specified for Option 1 of the Commissions Policy Statement on Engineering Expertise on Shift. If this option is used for a shift, then the separate STA position may be eliminated for that shift.
The Operations Manager, Mike Roder, informed me that they do not plan to routinely utilize the dual role SRO/STA option. The current plan is to man a five shift rotation in operation during/post plant restart. The current list of individuals that are qualified STA is as follows:
- Eric Horvath (STA)
- Paul Wadsworth (STA)
- Bill Bentley (STA)
- Bob Lakis (STA)
- Randy Patrick (STA)
Of this group, Paul Wadsworth is currently on rotation with Radiation Protection, but is current with all his crew training. Bill Bentley has taken a job outside of operations and does not plan on maintaining his license or STA qualification.
During Operation in Modes 1-4, the Davis-Besse operations shift composition includes four SROs: Shift Manager, Unit Supervisor, Field Supervisor, and Shift Engineer (or STA). If something happened that would require implementing the dual SRO/STA option, the Shift Manager would be the individual tasked to assume those roles. The licensee has three SROs in the pipeline that are currently pursuing STA qualifications.
This would result in having approximately 7 to 10 qualified individuals available near term to man a five shift rotation.
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The NRCs position on options for the implementation of the STA position is well documented in the following:
- Federal Register Notice, Dated 10/28/85
- Commission Policy Statement on Engineering Expertise on Shift, dated 10/28/85
- SECY-85-150 The licensee has an adequate number of qualified STAs to man a five shift rotation and are implementing the STA position IAW with their Technical Specification.
The Panel determined that this item is closed.
Item 197 (Open) - Develop a communication plan with restart Qs and As. (06/17)
J. Shea is compiling the list of Q & As for review by the Panel and results will be forwarded to the Regional Administrators office.
Item 201 (Closed) - Coordinate with L. Gerke and ask her to call Rep. Kaptur's staff regarding the June 13, 2003, letter from Chairman Diaz to Kaptur. The purpose of the call would be to update Rep. Kaptur on the recent issues with the HPI Pumps and provide information on NRC actions to review LER 2003-02. (06/20)
This item is covered by the Greater than Green HPI Comm. Plan and was addressed with the Executive Directors office this past Friday, 10/10.
The Panel determined that this item is closed.
Item 202 (Open) - Put a discussion of the actions the NRC took in reviewing concerns involving the reactor coolant pumps in the August 2003 newsletter. (07/15)
Information surrounding this issue will be collated and discussed at a future meeting, and will be included in the newsletter once the letter to Mr. Gunter/Gurdziel is issued.
Item 208 (Open) - Evaluate the need to call back CI regarding Allegation RIII-2002-A-0177 (D-B) after the OI Investigation is complete. (08/21)
Investigation is still ongoing.
Item 209 (Open) - Add author of Greenpeace 2.206 petition to the standard distribution list on documents for Davis-Besse. Then remove from distribution 90 days after the final NRC reply to the 10 CFR 2.206 Petition is signed out. (9/16) 5
All the authors have been added to the distribution list; removal date TBD following NRC reply being issued.
Item 210 (Open) - Contact cognizant personnel in NRC Research regarding the evaluation Research is performing about the combined effects of the deficiencies at Davis-Besse and coordinate a briefing of the Panel. (09/23)
Research was contacted and attended a meeting at HQs on 10/09. The Comm. Team was contacted for Q & As (GT 596). Mr. Grobe will brief the Panel on Thursday, 10/16.
Item 211 (Open) - (a) Issue a status report of the NOP test results thus far; (b) Issue a status report after the NOP inspection of record has been completed; (c) Issue a status report after the upper reactor vessel head and lower reactor vessel head tests are completed. The reports are to be forwarded to NRC Division of Engineering personnel.
(09/23)
This issue will be completed by licensee 10/15, and the results will be presented to the Panel within the next 2 weeks.
Item 212 (Open) - Determine whether the Communication Team has received all electronic and written correspondence from external sources. If there is reasonable confidence that the Communication Team has all the correspondence then develop a set of bullets explaining why there is reasonable confidence. (09/23)
Set of bullets still under development; item will be discussed at next Panel meeting on 10/16.
Item 213 (Open) - Update the punch list that will be used to ensure that NRC activities necessary for restart are accomplished with intermediate steps and their due dates.
(09/25)
Milestones are still being developed using 12/15/2003 as a reasonable target date for restart and completed matrix will be presented to the Panel next week.
Item 214 (Open) - Discuss with Region III Public Affairs Officers whether to include a discussion of the September 20, 2003, rally sponsored by the Union of Concerned Scientists in the next monthly NRC newsletter. (09/25)
The preliminary decision is that it is not appropriate to respond via the NRC newsletter; final disposition is pending.
Item 215 (Open) - Contact the Congressional Affairs office to obtain a current listing of Q & As on matters pertaining to restart and coordinate with Mr. Mendiola to provide an updated package to the Panel for review and incorporation into the Comm Plan. (10/02)
No update reported and item will be discussed at the next Panel meeting.
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Item 216 (Open) - Submit a TIA which addresses issues and questions related to the licensees 1991 10 CFR Appendix R exemption request regarding Alternative Shutdown (ASD) regulations. (10/02)
The TIA has been submitted to the Branch Chief for review.
Item 217 (Open) - Review and document the acceptability of the licensees withdrawal of the single safety group of control rods to provide a prompt trip response source of negative reactivity. The review will be documented in a resident inspection report.
(10/09)
This review is ongoing and will be documented in Inspection Report 05000346/2003022.
Item 218 (Open) - Set up a meeting to discuss the HPI Pump TIA and ensure that the TIA as-written reflects the needs of Region III personnel. (10/09)
This meeting is to decide on the inspection guide format and will be scheduled next week.
- 9. Discuss Process Plan Mrs. Lipa led a discussion of the Panel Process Plan. One item of note was on B.3.b, Assess available information... and the decision was made for Mr. Thomas to perform quarterly reviews (i.e., Aug-Oct, Nov-Jan) and present to the Panel for review and inclusion in the meeting minutes. The first review will be in 2 weeks. The remaining items in the latest revision to the plan were reviewed without further comment.
- 10. Discuss Items for Licensee Weekly Call The following items are proposed for discussion during the licensee weekly call on 10/15/2003:
Proposed date and site for the November 0350 public meeting; Confirm date for the Restart Oversight Panel meeting on 10/29/2003; Immediate Action Maintenance during NOP (NRC request);
HPI pump modifications and installation timelines; and Breaker Coordination evaluations/timeline.
- 11. Discuss/Update Milestones and Commitments The Panel reviewed and discussed upcoming milestones and commitments. The November 0350 Public Meeting date has tentatively been changed to 11/12, at the Oak Harbor High School, providing the site is available and the licensee concurs. The Completeness and Accuracy Inspection will start 10/20, with proposed public exit also on 11/12. A date is still pending for the Corrective Action Team Inspection public meeting.
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DAVIS-BESSE OVERSIGHT PANEL OPEN ACTION ITEM LIST Item Action Item (Date Assigned to Comments Number generated) 73 Send feedback form on Lipa/ 8/6 - Generate feedback after panel IMC 0350 procedure to Mendiola meetings reduced to once per week; IIPB (8/6) 8/29 - Discussed - no change; 10/1 -
Discussed; 11/7 - D Passehl sent email to C Carpenter and D Coe indicating that we would be able to perform a review of the draft IMC 0350 during the first quarter of 2003; 12/3-discussed; 01/03 - 2 parts, short part-C. Lipa with P. Harris, long part- B.
Dean; 01/07 - 2nd larger response will require meeting between all parties; 01/21 - Communications with P.
Harris; 01/31-Meeting with P. Harris on Feb 4; 02/11 - Many concerns identified by the panel for inclusion; 02/21 - July 1 due date for larger input; 07/01 - Request two month extension of due date; 07/22 - Due date extended to September 1; 09/25- Due date extended to January 1; 10/14 -
Discussed, Submittal needs to be coordinated to preclude sending information twice.
138 Evaluate the A. 01/31 - Ongoing; 02/21 - New EDO effectiveness of the Mendiola, Comm Plan for Crisis Update, A.
Comm Plan (01/07) C. Lipa Mendiola to review for inclusion; 10/14- Discussed, The new revised Comm. Plan is with the Panel Chairman for review. This item will be closed upon approval of the revised plan.
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DAVIS-BESSE OVERSIGHT PANEL OPEN ACTION ITEM LIST Item Action Item (Date Assigned to Comments Number generated) 147 Generate a list of items D. Passehl 01/31 - working; to consider after restart 02/11 - Include dates and deadlines to as well as transition Manual Chapter 0350 restart back to the normal inspections planner; 07/01 -
0350 when terminating Discussed; 7/22 - Dave has list with the 0350 Panel. The Christines comments; 08/05 -
items should include Discussed. Bring back 6 weeks; plans to augment 09/23 - Discussed; 09/30 - The Panel inspection of corrective decision is to separate this into three actions, inservice distinct listings: Inspection Schedule inspection, and safety items for both prior to and following culture monitoring. restart; Focus Areas for post restart; (01/09) and 0350 Panel termination criteria.
The Panel will approve listings; 10/14-Discussed, The inspection schedules and focus areas for post restart are incorporated in the punch list. When developed, the listing for 0350 Panel termination criteria will be presented to the Panel for approval.
178 Determine the type of C. Lipa 09/23 - S. Burgess was named to lead backlog assessment this inspection; 09/30 - Discussed, that will be performed reevaluation of resources and decision and by whom. Two on who will lead this inspection will be attributes need to be done on 10/2; 10/14-Discussed, The considered: (1) the backlog assessment will be conducted capability of the by S. Burgess and M. Parker, starting licensee to manage the 11/17/2003. Inspection plan will be backlog in an operating presented to the Panel on 10/21/2003.
environment; and (2) the impact of the backlog on equipment reliability. (03/04) 9
DAVIS-BESSE OVERSIGHT PANEL OPEN ACTION ITEM LIST Item Action Item (Date Assigned to Comments Number generated) 189 Collect Information on J. Stang 05/27-Discussed; 07/01 - The the Regulatory Millstone Order was reviewed and the Approach to Research approach is not appropriate. Bill also the Process to Ensure look at the South Texas approach; Proper Regulatory 07/15 -Discussed, title changed; 7/22 -
Footprint upon Restart Lead changed; 09/30 - Discussed, (05/16) history table populated with past 0350 decisions will be presented and decision on this criteria will be made by 10/9; 10/14-The Panel affirmed which tool to use, Item Closed.
193 Consider TIA on an J. Stang A concern was identified for the issue pertaining to 10 shutdown function performance goal of CFR 50 Appendix R maintaining reactor coolant level. An Section III-L, NRC safety evaluation report issued in "Alternative and 1991 apparently allows the licensee to Dedicated Shutdown maintain reactor coolant level above Capability." (05/27) the top of active fuel instead of maintaining level within the range of indication in the pressurizer; 7/1 -
John Hannon to determine if a TIA is necessary or the issue is moot. Sent in draft TIA to HQs J. Stang to review licensing basis first; 09/30 - Discussed, update will be presented on 10/2; 10/14-An update will be presented to the Panel at a future meeting.
196 Determine whether the J. Grobe 6/24 - Closed; 7/1 - Re-opened - see shift manager is meeting minutes for additional qualified to fulfill the information; 09/30 - Resolution will be shift engineer position available by 10/3; 10/14-This item was in an emergency and briefed and Closed, see internal whether there is an meeting minutes 10/14/03.
adverse impact on the licensee's emergency procedure Implemention. (06/17)
Item re-opened at 7/1 Panel meeting.
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DAVIS-BESSE OVERSIGHT PANEL OPEN ACTION ITEM LIST Item Action Item (Date Assigned to Comments Number generated) 197 Develop a J. Stang 6/24 - Lead changed; 08/21 - Lead communication plan changed; 09/30 - Discussed, list of Q with restart Qs and As. & As is being gathered for review and (06/17) forwarding to RA; 10/14-Discussed, J.
Shea is compiling the list of Q & As for review by the Panel and results will be forwarded to the RA.
201 Coordinate with L. T. Mendiola 6/24 - The Panel determined that Gerke and ask her to when the communication plan is call Rep. Kapturs staff developed for the preliminary regarding the June 13, significance determination for HPI 2003, letter from Pump issue that we consider Chairman Diaz to interfaces with those people who Kaptur. The purpose of receive the letter; 07/15 - Discussed; the call would be to 08/21 - Discussed; 09/30 - Discussed, update Rep. Kaptur on covered by GTG HPI Comm Plan, the recent issues with need to decide if this goes through the the HPI Pumps and EDOs or Chairmans office; 10/14-provide information on This item is covered by the Greater NRC actions to review than Green HPI pump Comm. Plan LER 2003-02.(06/20) and was addressed with the EDOs office this past Friday, 10/10/03, Item Closed.
202 Put a discussion of the J. Strasma 10/14-Discussed, Information actions the NRC took in surrounding this issue will be collated reviewing concerns and discussed at a future meeting.
involving the reactor coolant pumps in the August 2003 newsletter.
(07/15) 208 Evaluate the need to M. Phillips 10/14-Investigation is still ongoing.
call back CI regarding Allegation RIII-2002-A-0177 (D-B) after the OI Investigation is complete (08/21) 11
DAVIS-BESSE OVERSIGHT PANEL OPEN ACTION ITEM LIST Item Action Item (Date Assigned to Comments Number generated) 209 Add author of A. Saso 10/14-Discussed, All the authors have Greenpeace 2.206 been added to the distribution list; petition to the standard removal date TBD following NRC reply distribution list on being issued.
documents for Davis-Besse. Then remove from distribution 90 days after the final NRC reply to the 10 CFR 2.206 Petition is signed out. (9/16) 210 Contact cognizant J. Hopkins 10/14-Discussed, Research was personnel in NRC contacted and attended a meeting at Research regarding the HQs on 10/09. The Comm. Team was evaluation Research is contacted for Q & As (GT 596). Mr.
performing about the Grobe will brief the Panel on combined effects of the Thursday, 10/16.
deficiencies at Davis-Besse and coordinate a briefing of the Panel. (09/23) 211 (a) Issue a status report J. Jacobson 10/09-Discussed; Mr. Jacobson of the NOP test results provided the Panel with an update on thus far; (b) Issue a the licensees progress to date. Draft status report after the status reports are pending; 10/14-NOP inspection of Discussed, This issue will be record has been completed by licensee 10/15, and the completed; (c) Issue a results will be presented to the Panel status report after the within the next 2 weeks.
upper reactor vessel head and lower reactor vessel head tests are completed. The reports are to be forwarded to NRC Division of Engineering personnel.
(09/23) 12
DAVIS-BESSE OVERSIGHT PANEL OPEN ACTION ITEM LIST Item Action Item (Date Assigned to Comments Number generated) 212 Determine whether the J. Stang 10/14-Discussed, Set of bullets still Communication Team under development; item will be has received all discussed at next Panel meeting on electronic and written 10/16.
correspondence from external sources. If there is reasonable confidence that the Communication Team has all the correspondence then develop a set of bullets explaining why there is reasonable confidence.
(09/23) 213 Update the punch list C. Lipa 10/14-Discussed, Milestones are still that will be used to being developed using 12/15/2003 as ensure that NRC a reasonable target date for restart activities necessary for and completed matrix will be restart are presented to the Panel next week.
accomplished with intermediate steps and their due dates. (09/25) 214 Discuss with Region III C. Lipa 10/14-Discussed, The preliminary Public Affairs Officers decision is that it is not appropriate to whether to include a respond via the NRC newsletter; final discussion of the disposition is pending.
September 20, 2003, rally sponsored by the Union of Concerned Scientists in the next monthly NRC newsletter. (09/25) 13
DAVIS-BESSE OVERSIGHT PANEL OPEN ACTION ITEM LIST Item Action Item (Date Assigned to Comments Number generated) 215 Contact the J. Stang 10/14-No update.
Congressional Affairs office to obtain a current listing of Q &
As on matters pertaining to restart and coordinate with Mr.
Mendiola to provide an updated package to the Panel for review and incorporation into the Comm Plan. (10/02) 216 Submit a TIA which J. Lara 10/14-The TIA has been submitted to addresses issues and the Branch Chief for review.
questions related to the licensee's 1991 10 CFR Appendix R exemption request regarding Alternative Shutdown (ASD) regulations.
(10/02) 217 Review and document S. Thomas 10/14-Discussed, This review is the acceptability of the ongoing and will be documented in licensee's withdrawal of Inspection Report 05000346/2003022.
the single safety group of control rods to provide a prompt trip response source of negative reactivity. The review will be documented in a resident inspection report. (10/09) 218 Set up a meeting to C. Lipa 10/14-Discussed, This meeting is to discuss the HPI Pump decide on the inspection guide format TIA and ensure that the and will be scheduled next week.
TIA as-written reflects the needs of Region III personnel. (10/09) 14
RAM Item No. - E-22 Closed: Y Date of E-Mail - 02/19/03 at 8:16 am Author - Blanch Description of Issue - Has D-B changed its policy to require people to follow their chain of command to report safety concerns or concerns to the NRC?
Restart Checklist Item: N/A Description of Resolution - There never was a policy that required people to follow their chain of command to report safety concerns to the NRC. Although the licensee encouraged individuals to report concerns through the chain of command, individuals were also able to directly initiate a condition report. However, the licensee has changed its policies regarding the reporting of safety concerns. The licensee has initiated several policies to make it clear that individuals are encouraged to raise issues, and that they may go through several routes to raise their concerns. Although the preferred route remains going through an individuals supervisor to get the issue addressed, there are alternate routes also available to the individual. For example, the individual may still directly initiate a condition report. Also, an individual may initiate a concern in the employee concerns program, and that concern may be raised anonymously if the employee so desires.
RAM Item No. - L-42 Closed: Y Date of Letter - 07/15/02 Author - Lochbaum Description of Issue - Is the NRC confident that containment radiation monitors and other components inside containment will not be impaired by stuff in the air from postulated DBAs?
Restart Checklist Item: N/A Description of Resolution - The containment radiation monitor referenced in the letter is designed to provide information to the operators on radiation levels inside containment during normal operations. It is not designed to operate during a postulated DBA. In fact, the SFAS signal would isolate the sample lines, rendering the system inoperable. Although the letter referenced other components inside containment, there is no reference to what those components may be. Assuming the writer intended this to refer to components inside containment required to operate during or following a postulated DBA, those components are designed to meet 10 CFR 50.49 environmental qualification requirements, and are qualified as such. As noted in the review of the containment radiation monitors referenced by the author, those monitors were never inoperable, even with the stuff in the air.
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RAM Item No. - L-79 Closed: Y Date of Letter - 12/05/02 Author - Gurdziel (G-15)
Description of Issue - If there has been leakage of reactor coolant from the lower incore welds, the contingency repairs proposed by FENOC would exacerbate the potential for boric acid attack of the lower vessel head and incore monitoring wires.
Restart Checklist Item: N/A Description of Resolution - The NRC staff did not review the methodology for contingency repairs at this time because the results of the licensees Normal Operating Pressure/Near Operating Temperature (NOP/NOT) test was that there was no indication of reactor coolant leakage from the incore monitoring instrumentation nozzles. Given these test results, the licensee does not plan to perform any repairs of the nozzles.
Reference Material - NRC Inspection Report No. 50-346/03-23.
RAM Item No. - C-07 Closed: Y Description of Issue - Ongoing phase 3 observations of management and human performance following restart.
Description of Resolution - This item is being deleted from the RAM because it is a post-restart item and not a restart item, whereas the RAM is the Restart Action Matrix.
RAM Item No. - SUP-20 Closed: Y Description of Issue - Review of Licensee Control Systems for Identifying, Assessing, and Correcting Performance Deficiencies: Evaluate the effectiveness of the organization's use of industry information for previously documented performance issues.
Description of Resolution - This area was reviewed as part of the Programs Phase II inspection, which is documented in NRC Inspection Report 50-346/03-09. The inspectors verified that the Discovery Action Plan appropriately reviewed applicable regulatory, industry, and licensee guidance, as well as related Condition Reports and corrective actions, and had identified significant issues affecting the operating experience assessment program. The inspectors concluded that the review was critical and thorough. Furthermore, the inspectors concluded that the overall recommended corrective actions contained in the Integrated Action Plan report reasonably addressed significant program weaknesses identified by the licensee.
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Reference Material - NRC Inspection Report 50-346/03-09 (ADAMS Accession No.
ml031880844).
RAM Item No. - SUP-23 Closed: Y Description of Issue - Assessment of Performance in the Reactor Safety Strategic Performance Area: Inspection Preparation: Select a system(s) for focus using the plant specific individual plant evaluation (IPE) and issues identified as part of the performance information.
Description of Resolution - The Safety System Design and Performance Capability Inspection selected the Service Water System, the 4160 volt Emergency Electrical Distribution System, and the High Pressure Injection System for review. The team reviewed the following attributes for these systems: (1) process medium (water, steam, and air); (2) energy sources; (3) control systems; and (4) equipment protection. The team verified that procedural instructions to operators were consistent with the operator actions required to meet, prevent, and/or mitigate design basis accidents. The teams review considered requirements and commitments identified in the Updated Final Safety Analysis Report (UFSAR), Technical Specifications (TS),
design basis documents, and plant drawings. This review further verified that the required support functions for the selected systems would be available.
The team verified that the system needs for the selected systems were met. The supply of air, water, steam, and electrical power required by the TS were verified through a review of the design of the selected systems, and those systems providing support functions.
The team verified equipment for the selected systems required to operate and/or change state during accidents and events would have control power available. The team further reviewed the adequacy of alarm setpoints and verified that necessary instrumentation and alarms were available to operators for making necessary decisions in coping with postulated accident conditions. In addition, the team verified that the systems standby alignments were consistent with assumptions in the operating procedures as well as design and licensing basis assumptions.
Reference Material - NRC Inspection Report No. 50-346/02-14 (ADAMS Accession No.
ml030630314).
RAM Item No. - SUP-31 Closed: Y Description of Issue - Assessment of Performance in the Reactor Safety Strategic Performance Area: Key Attribute - Design: Select several modification to the system for review and determine if the system is capable of functioning as specified by the current design and licensing documents, regulatory requirements, and commitments for the facility.
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Description of Resolution - The Safety System Design and Performance Capability Inspection selected the Service Water System, the 4160 volt Emergency Electrical Distribution System, and the High Pressure Injection System for review. The inspectors reviewed the selected systems including a review of calculations, drawings, specifications, vendor documents, Updated Final Safety Analysis Report, TS, emergency operating procedures, and temporary and permanent modifications. The NRC inspections concluded that the licensees Latent Issues Reviews were performed in a manner sufficient to reasonably determine whether or not systems were capable of performing their safety functions during future plant operation.
Reference Material - NRC Inspection Report No. 50-346/02-14 (ADAMS Accession No.
ml030630314).
RAM Item No. - SUP-49 Closed: Y Description of Issue - Assessment of Performance in the Reactor Safety Strategic Performance Area: Key Attribute - Configuration Control: Perform a walkdown of the selected system. In addition, if the selected system does not directly have a containment over-pressure safety function (such as containment spray), conduct an additional review of such a system.
Independently verify that the selected safety system is in proper configuration through a system walkdown. Review temporary modifications to ensure proper installation in accordance with the design information.
Description of Resolution - Walkdowns of three selected systems were performed as part of the Safety System Design and Performance Capability Inspection. The selected systems were the Service Water System, the 4160 volt Emergency Electrical Distribution System, and the High Pressure Injection System. The team reviewed the following attributes for these systems: (1) process medium (water, steam, and air); (2) energy sources; (3) control systems; and (4) equipment protection. The team verified that procedural instructions to operators were consistent with the operator actions required to meet, prevent, and/or mitigate design basis accidents. The teams review considered requirements and commitments identified in the Updated Final Safety Analysis Report (UFSAR), Technical Specifications (TS), design basis documents, and plant drawings. This review further verified that the required support functions for the selected systems would be available.
The team verified that the system needs for the selected systems were met. The supply of air, water, steam, and electrical power required by the TS were verified through a review of the design of the selected systems, and those systems providing support functions.
The team verified equipment for the selected systems required to operate and/or change state during accidents and events would have control power available. The team further reviewed the adequacy of alarm setpoints and verified that necessary instrumentation and alarms were available to operators for making necessary decisions in coping with postulated accident conditions. In addition, the team verified that the systems standby alignments were consistent with assumptions in the operating procedures as well as design and licensing basis assumptions.
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Reference Material - NRC Inspection Report No. 50-346/02-14 (ADAMS Accession No. ml030630314) 19