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Category:Letter
MONTHYEARML24219A0262024-08-12012 August 2024 Request for Withholding Information from Public Disclosure IR 05000390/20240022024-08-0707 August 2024 Integrated Inspection Report 05000390/2024002 and 05000391/2024002 Rev ML24204A2652024-07-25025 July 2024 Regulatory Audit Summary Related to Request to Revise Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter ML24170A8002024-07-15015 July 2024 Issuance of Amendment Nos. 168 and 74 Regarding Revision to Technical Specification Table 1.1-1 for Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts IR 05000390/20244402024-07-12012 July 2024 95001 Supplemental Inspection Supplemental Report 05000390-2024440 and 05000391-2024440 and Follow-Up Assessment Letter ML24131A0012024-07-0202 July 2024 Issuance of Amendment Nos. 167 and 73 Regarding Adoption of Technical Specification Task Force Traveler TSTF-427-A, Revision 2 CNL-24-052, Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-06-27027 June 2024 Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-24-018, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS2024-06-25025 June 2024 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc IR 05000390/20240012024-05-14014 May 2024 Integrated Inspection Report 05000390/2024001 and 05000391/2024001 CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000391/20240072024-04-30030 April 2024 Assessment Follow-up Letter for Watts Bar Nuclear Plant, Unit 2 – Report 05000391/2024007 ML24120A1182024-04-29029 April 2024 – Notification of NRC Supplemental Inspection (95001) and Request for Information CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 CNL-24-010, License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19)2024-04-17017 April 2024 License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19) CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update ML23319A2452024-01-29029 January 2024 Issuance of Amendment Nos. 366 and 360; 164 and 71 Regarding the Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML24008A2462024-01-18018 January 2024 Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions CNL-24-016, Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-01-10010 January 2024 Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-23-052, Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability2024-01-0909 January 2024 Application to Adopt TSTF-427-A, Revision 2, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability CNL-23-062, Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018)2024-01-0808 January 2024 Application to Revise the Technical Specifications Section 3.8.2, AC Sources-Shutdown, to Remove Reference to the C-S Diesel Generator (WBN-TS-23-018) ML23346A1382024-01-0303 January 2024 Regulatory Audit Summary Related to Request to Increase the Number of Tritium Producing Burnable Absorber Rods CNL-23-069, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000390/20234412023-12-21021 December 2023 Plantfinal Significance Determination for a Security-Related Greater than Green Finding, Nov, and Assessment Follow-up, 05000390-2023441 and 05000391-2023441-Public CNL-23-036, Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)2023-12-18018 December 2023 Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08) IR 05000390/20234042023-12-14014 December 2023 Security Baseline Inspection Report 05000390/2023404 and 05000391/2023404 CNL-23-001, Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01)2023-12-13013 December 2023 Rebaseline of Sections 3.1 and 3.2 of the Technical Specifications (WBN-TS-23-01) ML23293A0572023-12-0606 December 2023 Issuance of Amendment Nos. 163 and 70 Regarding Adoption of TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control IR 05000390/20230102023-11-30030 November 2023 RE-Issue Watts Bar Nuclear Plant - Biennial Problem Identification and Resolution Inspection Report 050000390/2023010 and 05000391/2023010 and Apparent Violation CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20230032023-11-13013 November 2023 Integrated Inspection Report 05000390/2023003 and 05000391/2023003 and Apparent Violation ML23312A1432023-11-0808 November 2023 Submittal of Dual Unit Updated Final Safety Analysis Report (UFSAR) Amendment 5 CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-059, Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-2023-09-20020 September 2023 Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 ML23251A2002023-09-11011 September 2023 Request for Withholding Information from Public Disclosure for Watts Bar Nuclear Plant, Units 1 and 2 CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 IR 05000390/20230052023-08-30030 August 2023 Updated Inspection Plan for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390/2023005 and 05000391/2023005 ML23233A0042023-08-28028 August 2023 Proposed Alternative to the Requirements of the ASME Boiler and Pressure Vessel Code for Upper Head Injection Dissimilar Metal Butt Welds IR 05000390/20230022023-08-16016 August 2023 Reissue - Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2023002 and 05000391/2023002 ML23220A1582023-08-0909 August 2023 Integrated Inspection Report 05000390/2023002 and 05000391/2023002 CNL-23-045, License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010)2023-08-0707 August 2023 License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts (WBN-TS-23-010) CNL-23-028, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06)2023-08-0202 August 2023 Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06) ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills IR 05000390/20230112023-07-24024 July 2023 Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000390 2023011 and 05000391 2023011 CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions 2024-08-07
[Table view] Category:Regulatory Guide
MONTHYEARML0803904151979-10-15015 October 1979 Proposed Revision 2 to Regulatory Guide 1.97, Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident, Draft 1 ML0734102491978-03-0707 March 1978 Transmittal of Revision 1 to Regulatory Guide 1.97, a Clearer Basis for Development Initial Response 1979-10-15
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Text
SRN E UNITED STATES NUCLEAR REGULATORY COMMISSION
- .WASHINGTON, D. C. 20555 MAR 07 1978 Docket Nos.
Tennessee Valley Authority ATTN: Mr. N. B. Hughes Manager of Power 830 Power Building Chattanooga, Tennessee 37401 Gentlemen:
SUBJECT:
REVISION 1 TO REGULATORY GUIDE 1.97 As a result of recent discussions and correspondence concerning Revision 1 to Regulatory Guide 1.97, the staff has developed more specific guidance to assist you in responding to our letter dated October 18, 1977.
This enclosed guidance provides a clearer basis for the development of your initial response. Its issuance, in our opinion, precludes the need for additional meetings to discuss the guide. Please let us know, however, if you have further questions or if you feel that further meetings are necessary.
In order to continue the effort involved in implementation of Regulatory Guide 1.97, we require that you submit the information described in our October 18, 1977 letter by May 1, 1978.
Sincerely,
'Steven A.V'gajf ef Light Water Reactors Branch 4 Division of Project Management Enclosure.:
As stated CcS:
Listed on page 2
'K
Tennessee Valley Authority MAR 0 7 1978.
CCS:
Herbert S. Sanger, Jr. Esq.
General Counsel Tennessee Valley Authority 400 Commnerce Avenue E liB 33 Knoxville, Tennessee 37902 Mr. E. G. Beasley Tennessee Valley Authority W9C165, 400 Cormmerce Avenue Knoxville, Tennessee 37902 Mr. Wesley Byrd, Project Manager Tennessee Valley Authority 303 Power Building Chattanooga, Tennessee 37401
- 1. The analysis described in position C.1 and C.2 should include the followina:
a.. For each accident analyzed in Chapter 15 of the PSAR, describe
ýhow the proposed accident monitoring instrumentation will meet each provision of Positions C.l.a through C.l.f. Instru-mentation provided in response to Position C.l.f shall include appropriate monitors-of radioactive release rates through identifiable release points.
- b. Provide a specific reference and/or detailed description of how each instrument or group of instruments will satisfy the provisions of Positions C.4 through C.17. A general statement that a Position will be met is not sufficient.
- 2. Implementation of Position C.3 of Regulatory Guide 1.97 These guidelines provide a framework for the specific selection of instruments for worst-case conditions. These refer to situations where system performance is degraded such that coolant and containment pressures, and radiation levels in containment and in releases, greatly exceed values established by analyses of the postulated accidents listed in Chapter 15.
These worst case conditions may stem from several types of causes which. have been identified in risk assessments (see WASH-1400 for one assessment of dominant event sequences in two reactors). The four measurements required by Position C.3 are considered to provide
adequate informO11. to th* operator to meet Position C.l.f of the guide for accidert situaU.ions covered by C.3 ýsee. General below).
Additional types of measurements may, however. be appropriate where, for a specific reactor design, the staff has-identified accident sequences whhere operator a,.,iareness of the situations considered in Position C.3 ,would not otherwise be likely.
Three of the fo:ir measurements called for in Position C.3 are specific; the fourth is nat (monitoring radioactivity release rates through identifiable release points). Listed below is supplemental guidance lor C.3.d.
- a. General: The. intent is to monitor rates of releases for the worst-case conditions discussed above. The intent is to provide an assessment canoability that. will satisfy Objective 6 of the Discussion ('"allow for early indication of the need to initiate action necessarv to protect the public and' for an estimate of the magnitude of the impending event").
b.. Identifiable release points: Identifiable release points should include:'
(1) For Fi! in GW B.s (a) Auxiliary building ventilation exhausts from areas where, (i) ECCS enuipment is housed and (ii) Containment penetrations are located.
iOther release points may be determined to be imuportant as a result of the analyses perrfo- rfrd in conformance with Position C.l. This matter is to be addressed in connection withPhase II reviews (implementation of other Provisions of F'eoulatory Guide 1.97, the scope of --hich.for oreating reactors ,-ill be determined, on a case-by-.case basis)
(b) Containment purge line exhaust-downstream of filters, if any.
(c) Annulus exhaust downstream of filters; if any.
(2) In addition, for BWRs (a) Air ejector exhausts imme'diately downstream of the air ejectors.
- c. Release Rates: The instrumentation need not have the capability to identify the rate of release of specific isotopes; rather the objective should be to have the capability to estimate the order of magnitude of the releases. In addition, these instruments will have the capability to estimate the rate of release of I vs. noble gas activity.
Tables VII 1-2, 1-3 and 1-4 of WASH-1400 are acceptable as a basis for establishing the initial airborne inventory of isotopes within the containment. The CORRAL Code analyses of WASH-1400 may be used to estimate the behavior of the activity within the containment.
This information can be used to estimate the rates and magnitudeof releases to the release points considered above [worst case scenarios that result in an immediate release and for which instrumentation is not practical or would not provide useful information (e.g., steam explosions) need not be considered]. An alternate approach would be. to determine the instrument requirements necessary to monitor releases that contain activityconcentrations equivalent to that in the undiluted containment atmosphere described above. In. all cases, the instrument proposed must be capable of measuring activity release rates between the upper limit of the normally installed instrumentation and the maximum release rate identified using one of the procedure described above.
- 3. The..schedule for iimplementation of Regulatory Guide 1.97 includes development of the identification of the characteristics including location, range, environment, etc., of instrumentation to follow the course of an accident. In its assessment of the applicants proposal the staff will consider the availability of the equipment described. However, the staff, recognizes that the schedule for installation of the equipment must include an allowance for development of equipment that is not currently commercially available, if equipment that is presently commercially available is not acceptable.