ML18031B188

Proposed Tech Specs,Deleting Tables Listing Primary Containment Penetration & Valves Subj to Certain Provisions of 10CFR50,App J

ML18031B188
Person / Time
Site:	Browns Ferry
Issue date:	02/05/1987
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18031B187	List: ML18031B186 ML18031B188
References
NUDOCS 8702180257
Download: ML18031B188 (16)

Text

ENCLOSURE 1 PROPOSED TECHNICAL SPECIFICATIONS REVISIONS BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 (TVA BFN TS 224) 87021 80257 870Z05 QP flDQCK 05000259 P PDR P

LIST OF TABLES (Cont'd)

TABLE Title ~Pa e Na.

4.2.E Minimum Test and Calibration Frequency for Drywell Leak Detection Instrumentation . 3.2/4.2-49 4.2.F Minimum Test and Calibration Frequency for Surveillance Instrumentation . 3.2/4.2-50 4.2.G Surveillance Requirements for Control Room Isolation Instrumentation. 3.2/4.2-52 4.2.H Minimum Test and Calibration Frequency for Flood Protection Instrumentation . 3.2/4.2-53 4.2.J Seismic Monitoring Instrument Surveillance Requirements 3.2/4.2-54 3 '-1 Minimum RHRSW and EECW Pump Assignment 3.5/4.5-11 3.5.I MAPLHGR Versus Average Planar Exposure 3.5/4.5-21 3.7.A Primary Containment Isolation Valves 3.7/4.7-25 3.7.B Testable Penetrations with Double 0-Ring Seals Deleted 3.7.C Testable Penetrations with Testable Bellows. Deleted 3.7.D Air Tested Isolation Valves. Deleted 3.7.E Primary Containment Isolation Valves which Terminate below the Suppression Pool Water Level. Deleted 3.7,F Primary Containment Isolation Valves Located in Water Sealed Seismic Class 1 lines Deleted 3.7.H Testable Electrical Penetrations Deleted 4.8.A Radioactive Liquid Waste Sampling and Analysis 3.8/4.8-9 4.8.B Radioactive Gaseous Waste Sampling and Analysis. 3.8/4.8-10 4.9.A.4.C Voltage Relay Setpoints/Diesel Generator Start . 3.9/4.9-16 3.11.A Fire Protection System Hydraulic Requirements. 3.11/4.11-10 6.8.A Minimum Shift Crew Requirements. 6.0-19 Vii BFN Unit 1

4 3.7/4.7 CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 4.7.A. Primar Containment 4.7.A.2.g (Cont'd)

The total leakage from all penetrations and isolation valves shall not exceed 60 percent of La per 24 hours. Leakage from containment isolation valves that terminate below suppression pool water level may be excluded from the total leakage provided a sufficient fluid inventory is available to ensure the sealing function for at least 30 days at a pressure of 54.6 psig. Leakage from containment isolation valves that are in closed-loop seismic class I lines that will be water sealed during a DBA will be measured but will be excluded when computing the total leakage.

BFN 3.7/4.7-7 Unit 1

THESE PAGES HAVE BEEN DELETED BFN 3.7/4.7-32 thru 40 Unit 1

LIST OF TABLES (Cont'd)

TABLE Title ~Pa e No.

4.2.E Minimum Test and Calibration Frequency for Drywell Leak Detection Instrumentation . 3.2/4.2-49 4.2.F Minimum Test and Calibration Frequency for Surveillance Instrumentation . 3.2/4.2-50 4.2.G Surveillance Requirements for Control Room Isolation Instrumentation. 3.2/4.2-52 4.2.H Minimum Test and Calibration Frequency for Flood Protection Instrumentation . 3,2/4.2-53 4.2.J Seismic Monitoring Instrument Surveillance Requirements 3.2/4.2-54 3.5-1 Minimum RHRSW and EECW Pump Assignment . 3.5/4.5-11 3.5.I MAPLHGR Versus Average Planar Exposure , 3.5/4.5-21 3.7.A Primary Containment Isolation Valves . 3.7/4.7-25 3.7.B Testable Penetrations with Double 0-Ring Seals Deleted 3.7.C Testable Penetrations with Testable Bellows. Deleted 3.7.D Air Tested Isolation Valves. Deleted 3.7.E Primary Containment Isolation Valves which Terminate below the Suppression Pool Water Level. Deleted 3.7.F Primary Containment Isolation Valves Located in Water Sealed Seismic Class 1 lines . Deleted 3.7.H Testable Electrical Penetrations Deleted 4.8.A Radioactive Liquid Waste Sampling and Analysis 3.8/4.8-9 4.8.B Radioactive Gaseous Waste Sampling and Analysis. 3.8/4.8-10 4.9.A.4.C Voltage Relay Setpoints/Diesel Generator Start . 3.9/4.9-16 3.11.A Fire Protection System Hydraulic Requirements. 3.11/4.11-10 6,8.A Minimum Shift Crew Requirements. 6.0-19 vii BFN Unit 2

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 4.7.A. Primar Containment 4.7.A.2.g (Cont'd)

The total leakage from all penetrations and isolation valves shall not exceed 60 percent of La per 24 hours. Leakage from containment isolation valves that terminate below suppression. pool water level may be excluded from the total leakage provided a sufficient fluid inventory is available to ensure the sealing function for at least 30 days at a pressure of 54.6 psig. Leakage from containment isolation valves that are in closed-loop seismic class I lines that will be water sealed during a DBA will be measured but will be excluded when computing the total leakage.

BFN 3.7/4.7-7 Unit 2

THESE PAGES HAVE BEEN DELETED BFN 3.7/4.7-32 thru 40 Unit 2

TABLE Title ~Pa e No.

4.2.E Minimum Test and Calibration Frequency for Drywell Leak Detection Instrumentation . 3,2/4.2-48 4.2.F Minimum Test and Calibration Frequency for Surveillance Instrumentation . 3.2/4.2-49 4.2.G Surveillance Requirements for Control Room Isolation Instrumentation. 3.2/4.2-51 4.2.H Minimum Test and Calibration Frequency for Flood Protection Instrumentation . 3.2/4..2-52 4.2eJ Seismic Monitoring Instrument Surveillance Requirements 3 '/4.2-53 3.5-1 Minimum RHRSW and EECW Pump Assignment . 3.5/4.5-11 3.5.I MAPLHGR Versus Average Planar Exposure 3.5/4.5-21 3.7,A Primary Containment Isolation Valves 3.7/4.7-24 3.7.B Testable Penetrations with Double 0-Ring Seals Deleted Testable Penetrations with Testable Bellows. Deleted 3.7.C'.7.D Air Tested Isolation Valves. Deleted 3.7.E Primary Containment Isolation Valves which Terminate below the Suppression Pool Water Levele ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ Deleted 3.7.F Primary Containment Isolation Valves Located in Water Sealed Seismic Class 1 lines Deleted 3.7.H Testable Electrical Penetrations Deleted 4.8.A Radioactive Liquid Waste Sampling and Analysis 3.8/4.8-9 4.8.B Radioactive Gaseous Waste Sampling and Analysis. 3.8/4.8-10 4.9.A.4.C Voltage Relay Setpoints/Diesel Generator Start . 3.9/4.9-15 3.11.A Fire Protection System Hydraulic Requirements. 3.11/4.11-10 6.8.A Minimum Shift Crew Requirements. 6.0-19 vii BFN Unit 3

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 4.7.A. Primar Containment 4.7.A.2.g (Cont'd)

The total leakage from all penetrations and isolation valves shall not exceed 60 percent of La per 24 hours. Leakage from containment isolation valves that terminate below suppression pool water level may be excluded from the total leakage provided a sufficient fluid inventory is available to ensure the sealing function for at least 30 days at a pressure of S4.6 psig. Leakage from containment isolation valves that are in closed-loop seismic class I lines that will be water sealed during a DBA will be measured but will be excluded when computing the total leakage.

BFN 3.7/4.7-7 Unit 3

THESE PAGES HAVE BEEN DELETED BFN 3.7/4.7-32 thru 40 Unit 3

ENCLOSURE 2 DESCRIPTION AND JUSTIFICATION BROWNS FERRY NUCLEAR PLANT (BFN)

Descri tion of Chan e Browns Ferry Nuclear Plant Technical Specifications for units 1, 2, and 3 are changed to delete tables 3.7.B, 3.7.C, 3.7.D, 3.7.E, 3.7.F, 3.7.G, and 3.7.H which list primary containment penetrations and valves subject to certain provisions of 10 CFR 50, Appendix J.

Reason for Chan e The deleted tables provide lists of primary containment penetrations and isolation valves. These are duplicated in the Appendix J leak rate testing program. Duplication of these detailed tables in the technical specifications creates an unnecessary administrative burden.

Justification for Chan e Browns Ferry Nuclear Plant Technical Specification 4.7.A.2 requires that the provisions of 10 CFR 50, Appendix J, be satisfied for BFN units 1, 2, and 3.

Furthermore, 10 CFR 50.54 (o) requires that all water-cooled power reactors meet the containment leakage test requirements set forth in Appendix J.

Appendix J of 10 CFR 50 defines the primary containment penetrations for -which Type B and Type C leak rate tests are required to be performed.

Lists of primary containment penetrations for which Type B tests must be performed and lists of primary containment isolation valves for which Type C tests must be performed are maintained for BFN units 1, 2, and 3 in the Appendix J program. Since the information being deleted from BFN technical specifications is contained in the Appendix J program, and since a test report listing the penetrations tested is required to be submitted for NRC review after each integrated leak rate test, no reductions in testing requirements or NRC review will result due to this change. The Standard Technical Specifications do not contain lists of primary containment penetrations for leak rate test requirements. Table 3.7.A, which lists primary containment isolation valves and their operability requirements, is being retained as in Standard Technical Specifications.

For the reason stated above, TVA has concluded that these proposed technical specification changes will not reduce the margin of nuclear safety.

t ENCLOSURE 3 DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION BROMNS FERRY NUCLEAR PLANT (BFN)

UNITS 1, 2, AND 3 Descri tion of Amendment Re uest The proposed amendment would change the technical specification for BFN units 1, 2, and 3 by deleting five tables. Three of the deleted tables identify BFN primary containment penetration with double 0-ring seals or bellows and electrical penetration which 10 CFR 50, Appendix J, Part II.G, requires Type B local leak rate tests to be performed. The other two deleted tables identify primary containment isolation valves for which 10 CFR 50, Appendix J, Part II.H, requires Type C leak rate tests be performed and which 10 CFR 50 Appendix J, Part III.B.2 (a) and (b), require to be leak tested, not as a fluid sealed system or as a fluid sealed system, whichever is appropriate.

Basis for Pro osed No Si nificant Hazards Consideration Determination The Commission has provided standards for determining whether a significant hazards consideration exists as stated in 10 CFR 50.92(c). A proposed amendment to an operating license for a facility involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident from any accident previously evaluated, or (3) involve a significant reduction in a margin of safety.

1. The proposed amendment will not involve a significant increase in the probability or consequences of an accident previously evaluated. This deletion of tables from BFN technical specifications is an administrative change to remove lists of primary containment penetrations and valves which must be leak rate tested in accordance with 10 CFR 50, Appendix J.

There is no change in the requirements of or BFN commitment to comply with the provisions of Appendix J of 10 CFR 50 and BFN technical specification 3/4.7.A.2. The appropriate lists are maintained in the BFN Appendix J program.

2. The proposed amendment will not create the possibility of a new or different kind of accident from any previously analyzed since it does not eliminate or modify any requirement or commitment to comply with the provisions of 10 CFR 50, Appendix J, or BFN technical specification 3/4.7.A.2.

3. The margins of safety will not be reduced since the requirements of and the BFN commitment to comply with the provisions of 10 CFR 50, Appendix J, and BFN technical specification 3/4.7.A.2 remain unchanged.

Since the application for amendment involves a proposed change that is encompassed by the criteria for which no significant hazards consideration exists, TVA proposes to determine that the proposed amendment does not involve a significant hazards consideration.