ML20071E364
| ML20071E364 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 03/03/1983 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20071E362 | List: |
| References | |
| NUDOCS 8303100191 | |
| Download: ML20071E364 (6) | |
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ATTAC19fENT 1 PROPOSED TECHNICAL SPECIFICATION CHANGES 9
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i 6303100191 830303 PDR ADOCK 05000338 P
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INSTRUMENTATION BASES RADIATION MONITORING INSTRUMENTATION (Continued) by the individual channels and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.
3/4.3.3.2 MOVABLE INCORE DETECTORS The OPERABILITY of the movable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core.
The OPERABILITY of this system is demonstrated by irradiating each detector used and normalizing its respective output.
Quarter-core flux maps, as de[k(ne)d in WCdk,8648, June 1976, may be used the purpose of measuricg F Z or F a full incore flux map is For f
used.
in recalibration of the excore neutron flux detection system, and full incore flux maps or symmetric incore thimbles may be used for monitoring the QUADRANT POWER TILT RATIO when one Power Range Channel is inoperable, i-3/4.3.3.3 SEISMIC INSTRUMENTATION The OPERABILITY of the seismic instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety.
This capability is required to permit comparison of the measured response to that used in the design basis for the facility to determine if plant shutdown is required pursuant to Appendix "A" of 10 CFR Part 100.
The instrumentation is generally consistent with the recommendations of Regulatory Guide 1.12
" Instrumentation for Earthquakes," April 1974.
3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION t
The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a-result of routine or accidental release of t
radioactive materials to the atmosphere.
This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23 "Onsite Meteorological Programs," February 1972. A meteorological data collection program as described above is necessary to meet the requirements of subparagraph 50.36(a)(2) of 10 CFR Part 50, Appendix E to 10 CFR Part 50, and 10 CFR Part 51.
3/4.3.3.5 AUXILIARY SHUTDOWN PANEL MONITORING INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control room.
This capability is required in the event control room habitability is lost and is consistent with General Design Criterion 19 of 10 CFR 50.
NORTH ANNA - UNIT 1 B 3/4 3-2
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APPENDIX B TO FACILITY OPERATING LICENSE NO. NPF-4 NORTH ANNA POWER STATION, UNIT NO. 1 VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-338 ENVIRONMENTAL PROTECTION PLAN DECEMBER 1980 l
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1 APPENDIX B TO FACILITY OPERATING LICENSE NO3. DPR-NPF-4, NPF-7 NORTH ANNA POWER STATION VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NOS. 50-338, 50-339 ENVIRONMENTAL PROTECTION PLAN.
DECEMBER 1980 i
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ATTACHMENT 2 DISCUSSION OF PROPOSED TECHNICAL SPECIFICATION CHANGE
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DISCUSSION OF PROPOSED TECHNICAL SPECIFICATION CHANGE On' December; 17, 1982, Vepco submitted the North Anna Radiological Effluent
'. Technical. Specifications (RETS) -for North Anna Units 1 and 2.to the Nuclear Regulatory Commission. With this submittal, various portions of the Appendix B. Environmental Technical Specifications were deleted because these portions were being inserted into the Appendix A. Technical Specifications.
- Recently, it has been determined that the ' portions of - the Environmental Technical-Specifications that remained after the RETS submittal could have been deleted because they either appeared. in the Appendix A Technical Specificaticns or were contained.in Part II -of the Appendir B Technical Specifications (Environmental Protection Plan)'.
This proposed change:is to delete the remaining portions of the Environmental Technical Specifications that were not deleted in the December 17, 1982 RETS submittal.
Environmental-Technical Specification Section 3.1.4 can be deleted because
-Meteorological Monitoring is included in Appendix A Technical Specification - Section 3.3.3.4.
The portion of the Appendix B Bases describing the meteorological data collection program will be included in the Appendix A Bases Section 3/4.3.3.4.
The rest of Section 3.0 of Appendix B had no environmental surveillance information in it or was included in RETS or Part II of Appendix B.
There are no Non-Radiological Limiting Conditions for Operation in Section 2.1 and no Special Surveillance and Study Activities in Section 4.0 of Appendix B, so thase sections can be deleted.
Due to Sections 2.0, 3.0 and 4.0 now being deleted, there is no need for a Table of Contents, Definitions, or Administrative Controls in the Appendix B Environmental Technical Specifications.
By deleting all of Part I of the Appendix B Technical Specifications (Environmental Technical Specifications) Part II of the Appendix B Technical Specifications (Environmental Protection Plan) can be changed to Appendix B Technical Specifications.
Deleting the Appendix B Part I Environmental Technical Specifications in no way reduces the margin-of safety at North Anna Units 1 and 2 because the Radiological Environmental Technical Specifications will now he contained in the Appendix A
Technical Specifications.
The Appendix B
Technical l
Specifications (Environmental Protection Plan) will remain for non l
radiological environmental activities.
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