ML19260D682: Difference between revisions
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VIRGINIA E LEC~rHIC AND Powr n Co.eAxy Hrcruxoxo,VInors tA 202f,1 February 8, 1980 | VIRGINIA E LEC~rHIC AND Powr n Co.eAxy Hrcruxoxo,VInors tA 202f,1 February 8, 1980 Mr. Harold R. Denton, Director Serial No. 015C Office of Nuclear Reactor Regulation PO/FHT:baw U. S. Nuclear Regulatory Commission Docket No. 50.-338 Washington, D. C. 20555 License No. NPF-4 | ||
Mr. Harold R. Denton, Director Serial No. 015C Office of Nuclear Reactor Regulation PO/FHT:baw U. S. Nuclear Regulatory Commission Docket No. 50.-338 Washington, D. C. 20555 License No. NPF-4 | |||
==Dear Mr. Denton:== | ==Dear Mr. Denton:== | ||
Lessons Learned Short Term Requirements North Anna Power Station Unit 1 As stated in our letter Serial No. 015A, dated January 31, 1980, Lessons learned Short Term Requirement 2.1.6.a. Intestrity of Systems Outside Containment Likely to Contain Radioactive Materials has been implemented at North Anna Unit 1. A report of the leakage measurements and estimates is attached. | Lessons Learned Short Term Requirements North Anna Power Station Unit 1 As stated in our letter Serial No. 015A, dated January 31, 1980, Lessons learned Short Term Requirement 2.1.6.a. Intestrity of Systems Outside Containment Likely to Contain Radioactive Materials has been implemented at North Anna Unit 1. A report of the leakage measurements and estimates is attached. | ||
If you have any questions or require additional information, please contact this office. | If you have any questions or require additional information, please contact this office. | ||
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.y C. *.. Stallings Vice President-Power Supply and Production Operations cc: Mr. James P. O'Reilly 19AJ 266 gg02110 53f 9 | .y C. *.. Stallings Vice President-Power Supply and Production Operations cc: Mr. James P. O'Reilly 19AJ 266 gg02110 53f 9 | ||
Virginia Electric and Power Company Docke t No. 50-338 North Anna Power Station Unit 1 Lessons Learned Short Term Requireeents NUREG 0578 Section 2.1.6.a. | Virginia Electric and Power Company Docke t No. 50-338 North Anna Power Station Unit 1 Lessons Learned Short Term Requireeents NUREG 0578 Section 2.1.6.a. | ||
Leak Rate Testing Pursuant to Section 2.1.6.a of NUREC 0578 has been comple ted. | Leak Rate Testing Pursuant to Section 2.1.6.a of NUREC 0578 has been comple ted. | ||
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Post-accident hot leg sample line 0.0 GPD Process Vent : | Post-accident hot leg sample line 0.0 GPD Process Vent : | ||
The process vent operates at a sub-atmospheric pressure; it was not tested for leakage. | The process vent operates at a sub-atmospheric pressure; it was not tested for leakage. | ||
NOTE: All leaks were identified and documented for repair at a practical time. The remainder of high head SI is covered under the Primary System Leak Rate periodic test performed every 72 hours; unidentified leakage is less | NOTE: All leaks were identified and documented for repair at a practical time. The remainder of high head SI is covered under the Primary System Leak Rate periodic test performed every 72 hours; unidentified leakage is less than 1 gpm for the entire CVCS & RCS. -- - | ||
than 1 gpm for the entire CVCS & RCS. -- - | |||
i9AJ 268}} | i9AJ 268}} | ||
Revision as of 21:21, 1 February 2020
| ML19260D682 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 02/08/1980 |
| From: | Stallings C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0578, RTR-NUREG-578 NUDOCS 8002110578 | |
| Download: ML19260D682 (3) | |
Text
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VIRGINIA E LEC~rHIC AND Powr n Co.eAxy Hrcruxoxo,VInors tA 202f,1 February 8, 1980 Mr. Harold R. Denton, Director Serial No. 015C Office of Nuclear Reactor Regulation PO/FHT:baw U. S. Nuclear Regulatory Commission Docket No. 50.-338 Washington, D. C. 20555 License No. NPF-4
Dear Mr. Denton:
Lessons Learned Short Term Requirements North Anna Power Station Unit 1 As stated in our letter Serial No. 015A, dated January 31, 1980, Lessons learned Short Term Requirement 2.1.6.a. Intestrity of Systems Outside Containment Likely to Contain Radioactive Materials has been implemented at North Anna Unit 1. A report of the leakage measurements and estimates is attached.
If you have any questions or require additional information, please contact this office.
Very truly yours, v' ),7.xS:Hm.
w %
.y C. *.. Stallings Vice President-Power Supply and Production Operations cc: Mr. James P. O'Reilly 19AJ 266 gg02110 53f 9
Virginia Electric and Power Company Docke t No. 50-338 North Anna Power Station Unit 1 Lessons Learned Short Term Requireeents NUREG 0578 Section 2.1.6.a.
Leak Rate Testing Pursuant to Section 2.1.6.a of NUREC 0578 has been comple ted.
A system review identified safety injection and outside recirc spray as the only accident mitigation systems outside containment that would carry highly radioactive fluids af ter a severe accident. Non-mitigation systems that would carry highly radioactive fluids af ter a severe accident are boron recovery (de-gas mode only), containment atmosphere clean-up, gaseous waste, sampling (hot leg post-accident sample line only), liquid waste (sumps to HLLW drains tanks), and process vent.
Gaseous systems were tested using a volumetric leakage compensation technique with test instrumentation already on site. Adequate test apparatus was not available for accurate leak-rate testing of liquid systems; these were pressurized to normal operating pressure (or greater) and visually in-spected for leakage.
Leakage results are as follows:
Mitigation Systems Safety Injection:
Low Fead SI pump 1A & associated piping .1 GPD Low Head SI pump IB & associated piping 0.0 GPD Boron Injection Tank Flowpath 0.0 GPD Outside Recire Spray:
Outside Recire Spray Pump 2A & associated piping 0.0 GFD Outside Recirc Spray Pump 2B & associated piping .65 GPD Non-Mitigation Systems Boron Recovery (De-Gas Mode):
Gas Stripper Liquid .5 GPD Gas Stripper Vent Chillers & associated piping 0.0 SCFH Cas Stripper Compressors 6 SCFH Cas Stripper Surge Tank & associated piping 0.0 SCFR Containment Atmosyoure Clean-up Gaseous Waste: iO49 ') / 7 i , ' J c0/
Waste Gas Decay Tank 1B & associated piping 0.0 SCFH Waste Gas Decay Tank 1A & associated piping 3 SCFH Liquid Waste:
Sumps to HLLWDT 0.0 GPD
Sampling:
Post-accident hot leg sample line 0.0 GPD Process Vent :
The process vent operates at a sub-atmospheric pressure; it was not tested for leakage.
NOTE: All leaks were identified and documented for repair at a practical time. The remainder of high head SI is covered under the Primary System Leak Rate periodic test performed every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; unidentified leakage is less than 1 gpm for the entire CVCS & RCS. -- -
i9AJ 268