ML20205P318
| ML20205P318 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 10/27/1988 |
| From: | Bailey J GEORGIA POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-3.D.1.1, TASK-TM GN-1503, NUDOCS 8811080066 | |
| Download: ML20205P318 (5) | |
Text
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.e Geccg4 her Company
- ost Offo Box 2&2 F
W:ynesbora Gec g:a 30830 28 4 t fe 2
Birmmgham. Alabama 35202 Vogtle Project i
October 27, 1988 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk File: X7BC35 Washington. D. C.
20555 Log: GN-1503 PLANT V0GTLE - UNIT 2 NRC DOCKET NUMBER 50-425 CONSTRUCTION PERMIT NUMBER CPPR-109 SER CONFIRMATORY ITEM 43: TMI ITEM III,D.1.1 Gentlemen:
The Vogtle Electric Generating Plant (VEGP). Unit 2. has implemented a program to reduce leakage from systems outside containment which l
could potentially contain contaminated fluids during an accident or transient condition.
Thia program is in two phases.
Phase I will be implemented before fuel load and Phase 2 which is the same as previously implemented fer Unit 1. will be implemented at fuel load with the leakage to be reported prior to exceeding 5% power in accordance with NUREG 0737. III.D.1.1.
The Leakage Assessment program is designed to detect leakage from systems which would be used to bring the plant to a safe shutdown condition following an accident or transient.
The following systems were identified as having the potential for the leakage of contaminated fluids outside containment.
I a
Residual Heat Removal System ContainmentSpray(System (excludingNaOHSubsystem) excluding Boron b
Safety Injection e
d Chemical Volume and Control System (Letdown. Boron Recycle l
and Charging Pumps) e)
Post-Accident Processing System f)
Gaseous Waste Processing System g)
Nuclear Sampling System (Pressurizer Steam and Liquid Sample t
Lines. Reactor Coolant Sample lines. RHR Sample Lines. CVCS L
Demineralizer and Letdown Heat Exchanger Sample Lines Only)
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File: X7BC35 Log: GN-1503 October 27, 1988 Page two In Phase 1, leakage data is obtained during preoperational testing and efforts are being made to reduce leakage to zero prior to fuel load.
The Residual Heat Removal, Safety Injection, Chemical Volume Control, Post Accident Processing, and Nuclear Sampling Systems were pressuriud dt..*ing hot functional testing and system walkdowns were conducted to identify leaks.
Action was taken to repair the leaks with emphasis on repairing as many as possible during hot functional testing.
The Containment Spray System was walked down during the performance of its preoperational test, and leaks were identified and repaired at that time.
The Gaseous Waste Processing System will be tested using 2-4HA-01 procedure for the control of measurements, repair of leaks, and documentation of final leakrate.
The testing of this system is expected to be completed in December
- 1988, i
Phase 2 of the program will utilize VEGP surveillance procedures 55010-2 through 55016-2 to quantitatively measure the leakage from the components of the identified systems.
Af ter these results are reported, a continuing effort in conjunction with VEGP's Preventive Maintenance Program will be made to reduce all known leakage to a level as low as practical.
Surveillance will be repeated at each refueling to meet the reouirement of VEGP Technical Specification l
6.7.4.a.
I If any additional information is required, please do not hesitate to contact me.
Sincerely,
.k' J. A. Bailey Project Licensing Manager JAB /wkl xc:
NRC Regional Administrator NRC Resident Inspector P. D. Rice J. P. Kane R. A. Thomas B. W. Churchill, Esquire J. E. Joiner, Esquire J. B. Hopkins (2)
G. Bockhold, Jr.
R. J. Goddard, Esquire R. W. McManus l
Vogtle Project File l
d l
Georg a Power Corncany l
Rote 2. Box 299A Waynescoro. Georgd 30830 Teteceore 404 554 9961 404 724-0114 b M - h (e
- 1 Y g;,j.,,e C;*cary $4ry'Cel. Inc Post once 00: 2625
?le~;CIR!N
Vogtle Project i
t March 21, 1986 Director of Nuclear Reactor Regulation l
Files X7BC35 Attention: Mr. B. J. Youngblood PWR Project Directorate #4 Lost GN-842 i
Division of PWR Licensing A U. S. Nuclear Regulatory Commission Washington, D.C.
20555 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109 V0GTLE ELECMIC GENERATING PIANT - UNITS 1 AND 2 SER CONFIRMATORY ITEMS 43 & 50: TMI ITEM III.D.1.1 I
l
Dear Mr. Denton:
Attached for your staff's review is the VIX;P response to TMI Iten III.D.1.1,
($
Integrity of Systems outside Centainssat Likely to Contain Radioactive Material for PWRs.
The program referenced in the attachment is the program cited in paragraph 6.8.4(a) of the VEGP Technical Specifications.
If your staff requires any additional information, please do not hesitate to contact me.
1
- erely, J. A. Bailey Project Licensing Manager l
JAB /sa l'
Attachment xc:
R. E. Conway G. Bockhold, Jr.
R. A. Thomas NRC Resident Inspector i
J. E. Joiner, Esquire D. C. Teper i
B. W. Churchill, Esquire W. C. Ramsey M. A. Mille r (2)
L. T. Gueva B. Jones, Esquire Vogtle Project File P
.e
III.D.1.1 INTEGRITY OF SYSTEMS OtRSIDE CONTAINMENT LIKELY TO CONTAIN RADIOACTIVE MATERIAL FOR PRESSURIZED-WATER REACTORS AND BOILING-WATER REACTORS NRC Position Applicants shall implement a program to reduce leakage from systems outside containment that vould or could contain highly radioactive fluide during a serious transient or accident to as-low-as practical levels. The program shall include the followings (1) Immediate leak reduction (a) Implement all practical leak reduction seasures for all systems that could carry radioactive fluid outside of containment.
(b) Measure actual leakage rates with system in operation and report them to the NRC.
(2) Continuing Leak Reduction -- Establish and implement a program of preventive usintenance to reduce leakage to as-low-as-practical levels,.
This program shall include periodic integrated leak tests at intervals not to exceed each refueling cycle.
Response
VEGP will implement a program to reduce leakage from systems outside containment which could carry highly contaminated fluida during a serious accident or transient. This program will be initiated prior to consercial operation and will be performed in accordance with NUREG-0737, III.D.1.1.
The Leakage Assessment program is designed to detect leake ; from systems which would be used to bring the plant to a safe shutdown condition following a serious accident or transient.
Baseline leakrate data will be acquired during the Power Ascention test phase and will be used when the Leakage Assessment program is initiated to reduce leak rates to as low as reasonably achievable.
l The following systems were identified.as having potential for the leakage of contaminated fluids outside containment.
I a) Residual Heat Removal Systes b) Containment Spray System (escluding NaOH Subeystem) c) Safety Injection (excluding Boron Injection & Accumulators) d) Chemical Volume and control System (Letdown, Doron Recycle and Charging pumps) l e) Post-Accident Processing Systes f) Gaseous Waste Processing Systen
- 3) Nuclear Sampling System (Pressuriser steam and liquid samp1s lines.
l Reactor Coolant sample lines, RHR sample lines, CVCS Demineraliser and Letdown Heat Exchanger sample lines only) i
The Leakage Assessment program will utilize visual inspections of mechanical joints and seals of liquid systems and local leak rate tests (LLRT) on gaseous systems.
These inspections will be conducted during plant refueling outages.
The visual inspections will be conducted with the systes pressurized to normal operating pressure using the cystem fluid as the test medium.
The gaseous system will employ a LLRT test method, leakage will be identified by bubble testing of mechanical joints and seals. All leakage will be assessed and documented and compared against baseline data.
Corrective action will be taken prenptly if the seasured leakage is found to be unacceptable, but in all cases the criteria will be to reduce leakage to as-low-as-practical levels.
When the Leakage Assessment Program is implemented, it will be used in conjunction with the VEGP's Preventive Maintenance Program to keep leakage rates below the acceptable limits.
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l})tirlffl D COfrCSpOnd nCS Georgia Power d DATE:
October 21, 1988 RE:
Vogtle Unit 2 HFT Leak Inspection TO:
Harvey Handfinger FROM:
Mark J.
AJ1 uni Operations has performed a leakage inspection on the Safety Injection
- System, Nuclear Sampling System, Chemical Volume ano Control
- System, and the Residual Heat Removal System.
The results are listed per Attachment 1.
The following systems could not be inspected during HFT due to system configuration and status:
Reason Containment Spray Not placed in service Post Accident Sampling -
Present system configuration does not support placing it in service Waste Gas Processing Unable to detect leakage and system is not in service Please pursue with Project Licensing, an exemption of Technical Specification 6.7.4.A "primary Coolant Sources Outside of Containment" until 5%
thermal power is exceeded.
This is similar to the Unit 1 T.S.
exemption and allows Engineering Support to implement their engineering surveillance procedures to more accurately determine actual leakage.
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M.
W.
Horton L.
L.
Coursey S.
B.
Hall W.
F.
Kitchens W.
R.
Dunn 8.
O.
Carter l
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ATTACHMENT 1 Safety Injection /12c4/aJ 2HV88790 unmeasurable 2HV8879A 10/ml hour 2HV8878A 10 ml/ hour 2HV88788 10 ml/ hour 2HV8878C 350 ml/ hour 2HV88778 30 ml/ hour 2HV88798 20 ml/ hour 2-1204-U4-154 -
20 ml/ hour 2-1204-U4-156 -
20 ml/ hour 2-1204-X4-101 unmeasurable 2-1204-U4-023 -
unmeasurable 10 ml/ hour 2-1204-04-024 2-1204-U4-025 -
unmeasurable 2-FE0917 10 ml/ hour 490 ml/ hour Measurable I
Total
=
Unmeasurable < 10 ml/ hour Nuclear Sampling System /1212/SJ 2HV3507 60 ml/ hour 2HV3500 - 40 ml/ hour Total 100 ml/ hour
=
CVCS/1200/BG 2-1208-U4-001-RO1 - unmeasurable 2-PSV-8510A
- 30 ml/ hour 2-FT-138
- unmeasurable 2-1208-L-141 unmeasurable 2-1208-L-139
- unmeasurable 2-HV-8110 10 ml/ hour 2-1208-X4-027 10 ml/ hour 2-FV-110A
- unmeasurable 2-1208-U4-416
- unmeasurable 2-1208-U4-417
- unmeasurable 2-1208-U4-414 10 ml/ hour 2-1208-U4-415
- unmeasurable l
2-HV-81038
- unmeasurable 2-FT-144 10 ml/ hour Total = 70 ml/ hour measurable Unmeasurable < 10 ml/ hour i
a D
RHR Leaks 10-21-88 2-1205-X4-043 20 ml/ hour (1205) 2FE-0618 Flange 600 ml/ hour (1205) 2FV-618
- 36,000 ml/ hour (1205) 2FV-619 1,000 ml/ hour 2-1205-04-121 150 ml/ hour (1705) 2HV-87168 20 ml/ hour 2-1205-U4-12 Common Line 750 ml/ hour T-1205-U4-54 Common Line -
750 ml/ hour Total 39,290 ml/ hour
=
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