Letter Sequence Request |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
Results
Other: CNL-14-201, Response to Questions Regarding the Unit 1/Unit 2 As-Constructed Fire Protection Report, CNL-15-174, Submittal of Updated Pages for Unit 1/Unit 2 As-Constructed Fire Protection Report & License Condition 2.C(9) Addition Request, CNL-15-214, Updated Pages for As-Constructed Fire Protection Report, ML113500239, ML12207A080, ML13051A045, ML13081A002, ML13081A003, ML14265A449, ML15175A508
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MONTHYEARML1000800082010-01-11011 January 2010 Notice of Forthcoming Conference Call with Tennessee Valley Authority Sequoyah Nuclear Plant, Units 1 & 2; Watts Bar Unit 1 Project stage: Request ML1001914212010-01-11011 January 2010 Final Safety Analysis Report, Amendment 97 Project stage: Request ML1013701862010-05-14014 May 2010 OL - FW: Call Summary - TVA Clarification Call Project stage: Request ML1015401332010-06-10010 June 2010 Request for Additional Information Regarding Licensees Final Safety Analysis Report Amendment Related to Accident Dose Project stage: RAI ML1019402362010-06-18018 June 2010 Instrumentation and Controls Staff Information Requests Project stage: Request ML1018201562010-06-18018 June 2010 OL - Updated Open Items List Project stage: Request ML1015402502010-06-24024 June 2010 Request for Additional Information Regarding Licensees Final Safety Analysis Report Amendment Related to Nuclear Performance and Code Review, Plant Systems, and Testing (Tac Nos. ME2731 and ME3091) Project stage: RAI ML1016002782010-07-12012 July 2010 Request for Additional Information Regarding Licensees Final Safety Analysis Report Amendment Related to Accident Dose Project stage: RAI ML1019506102010-07-30030 July 2010 Request for Additional Information, Licensees Final Safety Analysis Report Amendment Related to Chapters 3.9.1, 3.9.2, and 3.9.3 Project stage: RAI ML1019404742010-07-30030 July 2010 Request for Additional Information, Licensees Final Safety Analysis Report Amendment Related to Chapter 10.4.7 Project stage: RAI ML1026305982010-09-28028 September 2010 Request for Additional Information, Regarding Final Safety Analysis Report Related to Sections 3.2 and 5.2 Project stage: RAI ML1029901502010-10-26026 October 2010 Cancelled - Notice of Meeting with (Tva), to Discuss Responses to the NRC Requests for Additional Information (Rals) for Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Project stage: RAI ML1035401772010-12-20020 December 2010 Notice of Meeting with Tennessee Valley Authority to Discuss Watts Bar Nuclear Plant, Unit 2, Final Safety Analysis Report Related to Section 7 Instrumentation and Control Project stage: Request ML1036101142010-12-21021 December 2010 Submittal of Pre-op Test Instruction Project stage: Request ML1101401972011-01-14014 January 2011 Notice of Meeting with Tennessee Valley Authority to Discuss Watts Bar Nuclear Plant, Unit 2, Final Safety Analysis Report Related to Section 7 Instrumentation and Control Project stage: Request ML1102801282011-02-0909 February 2011 Request for Additional Information, Regarding Final Safety Analysis Report Amendment Related to Section 9.5.1 Fire Protection System Project stage: RAI ML1106107452011-03-10010 March 2011 Request for Additional Information, Regarding Final Safety Analysis Report Related to Section 9.5.1 Fire Protection Report - Round 2 Project stage: RAI ML1107705372011-03-16016 March 2011 Instrumentation and Controls Staff Information Requests Project stage: Request ML1109104642011-04-13013 April 2011 Summary of Meeting with Tennessee Valley Authority to Discuss Watts Bar Nuclear Plant, Unit 2, Final Safety Analysis Report Related to Section 9.5.1 Fire Protection Project stage: Meeting ML1109607652011-04-25025 April 2011 Request for Additional Information Regarding Final Safety Analysis Report Related to Section 9.5.1 Fire Protection Round 3 Project stage: RAI ML11129A1582011-05-0606 May 2011 Request for Additional Information Regarding Fire Protection Report, Project stage: Request ML11165A1452011-05-18018 May 2011 OL - Commitments and Sser Open Items Project stage: Request ML1112404832011-05-23023 May 2011 Request for Additional Information Regarding Final Safety Analysis Report Related to Section 9.5.1 Fire Protection Round 4 Project stage: RAI ML1115201192011-05-26026 May 2011 Response to Request for Additional Information Regarding Fire Protection Report Project stage: Response to RAI ML1114506732011-05-26026 May 2011 July 14, 2011 Notice of Forthcoming Meeting with Tennessee Valley Authority (TVA) to Discuss Bellefonte Nuclear Plant, Unit 1, Digital Instrumentation and Control and Human Factors Project stage: Request ML11161A1282011-06-0707 June 2011 Safety Evaluation Report Supplement 22 (Sser 22) - Second Response to NRC Required Action Items Project stage: Request ML1115109792011-06-0808 June 2011 Request for Additional Information Regarding Final Safety Analysis Report Related to Section 9.5.1 Fire Protection Round 5 Project stage: RAI ML11186A8642011-07-0101 July 2011 Submittal of Report in Accordance with 10 CFR 26.719(c)(1) for Drug and Alcohol Testing Errors Project stage: Request ML11200A1092011-07-14014 July 2011 Meeting Slides - TVA Phase 0 Meeting Bln/Nrc Bellefonte Digital I & C Upgrades Project stage: Request ML11200A1152011-07-14014 July 2011 Meeting Slides - TVA Phase 0 Meeting with NRC Bellefonte Units 1 & 2 Main Control Room Modernization Project stage: Request ML1118235802011-07-21021 July 2011 Request for Additional Information Regarding Final Safety Analysis Report Related to Section 9.5.1 Fire Protection Group 6 Project stage: RAI ML1120000992011-07-22022 July 2011 July 14, 2011 Summary of Pre-Application Meeting with Tennessee Valley Authority Regarding Digital Instrumentation and Control and Human Factors for the Potential, Proposed Updated Operating License Application at Bellefonte Nuclear Plant, Project stage: Meeting ML1120303872011-07-27027 July 2011 Request for Additional Information Regarding Incore Instrumentation System Project stage: RAI ML11215A1322011-07-29029 July 2011 Response to Request for Additional Information Regarding June 28, 2011 NRC Audit- Steam Line Break (Slb) and Other Miscellaneous RAIs Project stage: Response to RAI ML11227A2572011-08-0505 August 2011 Request for Additional Information (RAI) Group 6 Regarding Fire Protection Report Project stage: Request ML11230A3852011-08-15015 August 2011 Transmittal of Revised Unit 1 / Unit 2 As-Designed Fire Protection Report Project stage: Request ML1124904742011-09-14014 September 2011 Request for Additional Information Regarding Final Safety Analysis Report Related to Section 9.5.1 Fire Protection Group 7 Project stage: RAI ML11286A0352011-09-30030 September 2011 OL - Additional Draft RAI on Fire Protection - Group 8 Project stage: Request ML11286A0382011-09-30030 September 2011 OL - Draft RAIs on Fire Protection - Group 8 Project stage: Request ML13060A2252011-09-30030 September 2011 Response to Request for Additional Information Group 7 Regarding Fire Protection Report, (TAC No. ME3091) (Public Version) Project stage: Response to RAI ML11306A0902011-10-28028 October 2011 Response to Request for Additional Information Group 8 Regarding Fire Protection Report Project stage: Response to RAI ML11322A1032011-11-30030 November 2011 WCAP-17529-NP, Rev. 0, System Requirements Specification for the Common Q Post Accident Monitoring System Project stage: Request ML1135002392011-12-20020 December 2011 Audit Report of Fire Protection Relating to Final Safety Analysis Report Accident Analyses Project stage: Other ML12054A0622012-03-13013 March 2012 Summary of Public Meeting with Tennessee Valley Authority Regarding Watts Bar Nuclear Plant, Unit 2, Final Safety Analysis Report Related to Fire Protection Project stage: Request ML1207905812012-03-23023 March 2012 Request for Additional Information Regarding Final Safety Analysis Report Related to Section 9.5.1, Fire Protection Group 8 Project stage: RAI ML12142A0262012-05-17017 May 2012 OL - Request for Additional Information Regarding Fire Protection Review Group 10 Project stage: RAI ML12153A3742012-05-30030 May 2012 Watts, Unit 2, Response to Request for Additional Information Project stage: Response to RAI ML12181A5312012-06-27027 June 2012 Resolution of Concerns with Fire Protection Report (FPR) Operator Manual Action (OMA) 732 and Response to Requests for Additional Information Project stage: Response to RAI ML12207A0802012-07-19019 July 2012 Resolution of Concerns with Fire Protection Report Operator Manual Action 732 - Commitment Schedule Update Project stage: Other ML13051A0452013-02-14014 February 2013 Updated Response to NRC Bulletin 2011-01, Mitigation Strategies Project stage: Other 2011-05-23
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Text
Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 August 15, 2011 10 CFR 50.4 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 2 NRC Docket No. 50-391
Subject:
WATTS BAR NUCLEAR PLANT (WBN) UNIT 2 - TRANSMITTAL OF REVISED UNIT 1 I UNIT 2 AS-DESIGNED FIRE PROTECTION REPORT (TAC NO. ME3091)
Reference:
TVA Letter to NRC dated August 5, 2011, "Watts Bar Nuclear Plant, Unit 2 -
Request for Additional Information (RAI) Group 6 'Fire Protection Report' (TAC NO.
ME3091)"
The purpose of this letter is to transmit a revision to the WBN Unit 1/Unit 2 Fire Protection Report (FPR) and to address two questions received from the Staff regarding the FPR Feasibility and Reliability evaluations (F&R evaluations) for Unit 2. Enclosure 1 contains the Unit 1/Unit 2 FPR in its entirety for completeness. Additionally, revision bars are utilized throughout the enclosed document to identify the changes. The main purpose of this FPR revision is to include the modifications required to reduce the number of Operator Manual Actions (OMAs) required for Unit 2 operation. provides an update to the summary listing of Fire Protection commitments that was submitted in the referenced letter. This update is based upon items addressed by this letter.
This summary listing contains a description of the commitment, the status (open or closed), as well as pertinent references (initiating, closing, etc.). The commitment date for one item has been updated based on the current project schedule.
The following provides the two NRC questions regarding the FPR OMA Feasibility and Reliability evaluations for Unit 2 and TVA's responses:
- 1. It appears the OMA times contained in the report are for each individual action and are not added up to show that the time required for all the actions that a specific AUO has to perform is less than the available time. In other words are the times cumulative or individual?
- 2. It appears the demonstrated travel time does not account for any margin.
- -(p
U.S. Nuclear Regulatory Commission Page 2 August 15, 2011 The following discussion is based on the F&R evaluations contained in the July 1, 2011 letter.
Some of the section numbers may change in the August 15, 2011 submittal, but the concepts/justifications will still be the same.
Question I The times quoted in the FPR Part VII, Section 8 for Unit 2 are cumulative times for all required actions based upon Unit 1 walkdowns (see Part VII, Section 8.2.a, last sentence). The walkdowns for Unit 1 were performed for each of the fire protection Abnormal Operating Instructions (AOIs) demonstrating the timing for the specific actions in that particular AOI in the order performed by that AOI. Even if multiple AOIs required the same actions by an operator, the OMA sequence was validated again in conjunction with validation of the OMAs performed by the other operators. The demonstrated times for the OMAs for a given AOI are cumulative times accounting for all required OMAs. Since the time of the Unit 1 validation, the OMAs have been categorized as either "green box" (required for safe shutdown) or "orange box" (important to safety). The validation walkdowns included all OMAs within a given AOI (both green and orange) and thus the times in the F&R evaluations are total cumulative times.
It appears the confusion lies in the presentation of the information in the FPR. FPR Part VII, Section 8 discusses the OMAs required for each fire room (e.g., for fire room 692-Al B, Section 8.3.1.3 for OMA 1047, Section 8.3.1.4 for OMAs 1159 and 1160, Section 8.3.1.5 for OMA 1164 and Section 8.3.1.6 for OMA 1165). These sections contain the Unit 1 demonstrated times for each OMA required for safe shutdown (i.e., green box) having a required performance time of less than 120 minutes, as validated by the associated AOI. Then, Section 8.3.1.7 describes the staffing required to accomplish all of the OMAs (i.e., green box and orange box) within the required time. The F&R of each green box OMA of required times less than 120 minutes is evaluated in its corresponding section (e.g., 8.3.1.3.a and 8.3.1.3.b for OMA 1047). For this fire room, OMA 1047 is the sole action performed by the designated AUO, and thus the demonstrated time for OMA 1047 used for both the F&R evaluations is quite clear.
However, for other fire rooms, the presentation of the information could be confusing. For example, fire room 737.0-AlA (FPR Section 8.3.25) requires AUO #3 to perform five actions (Section 8.3.25.12.c). They are the same five actions demonstrated for Unit 1. The discussion of F&R in Sections 8.3.25.3 through 8.3.25.11 discusses each action as if it were an individual, discrete action. In reality, the demonstrated times quoted in the sections (e.g., 8.3.25.11.a and 8.3.25.11.b) are the cumulative time used by the operator in performing not only that action, but also any preceding actions. The OMAs are not discussed/presented in the order performed by the AUO and thus the times do not appear to be cumulative even though in actuality they are cumulative. Additionally, the demonstrated times account for orange box OMAs (e.g., 1044) and OMAs with required times greater than 120 minutes even though these OMAs are not evaluated in the report.
In a few places the report shows the same time for two actions (e.g., OMAs 1022 and 1023 in Sections 8.3.15.3 and 8.3.15.4). In this case the time is cumulative for both actions to be performed. The actions are performed in the same area and thus only a single cumulative time was recorded.
U.S. Nuclear Regulatory Commission Page 3 August 15, 2011 Question 2 NUREG-1852 Section 4.2.2 describes two methods of ensuring adequate time is estimated for operator action performance time.
- a. Conservatively estimate the time to envelope all possible uncertainties. The second sentence at the top of page 4-4 indicates that 100% margin should be adequate (but not required) to envelope all uncertainties. The acceptance criteria in FPR Part V, Section 2.1.2.1.a uses this approach.
- b. Specifically account for each uncertainty and add additional time to the demonstrated performance time to account for the uncertainties applicable to each situation. The acceptance criteria in FPR Part V, Section 2.1.2.1.b uses this approach.
There are no new regulatory commitments in this letter. If you have any questions, please contact William Crouch at (423) 365-2004.
I declare under the penalty of perjury that the foregoing is true and correct. Executed on the 1 5 th day of August, 2011.
Respectfully, David Stinson Watts Bar Unit 2 Vice President
Enclosures:
- 1. Revised Unit I / Unit 2 As-Designed "Fire Protection Report
- 2. Summary Listing of Fire Protection Commitments cc (Enclosures):
U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 NRC Resident Inspector Unit 2 Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381