ML20195C026: Difference between revisions
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==Reference:== | ==Reference:== | ||
Andognini to Crutchfield letter dated May 17, 1988, RCP Stud Integrity | Andognini to Crutchfield {{letter dated|date=May 17, 1988|text=letter dated May 17, 1988}}, RCP Stud Integrity | ||
==Dear Sir:== | ==Dear Sir:== | ||
| Line 57: | Line 57: | ||
: 5. Replace degraded studs, if any, which do not pass acceptance criteria for continued operation. | : 5. Replace degraded studs, if any, which do not pass acceptance criteria for continued operation. | ||
3 Attachment Y is the tentative schedule for the "C" RCP leak repair during the July outage. | 3 Attachment Y is the tentative schedule for the "C" RCP leak repair during the July outage. | ||
ACCEPTANCE CRITERIA 0 Stud diameter greater than 3.20 inches O Leak repaired The existing analysis of acceptable stud diameters performed by the RCP manufacturer (Bingham-Willamette Company) has established 3.20 inches as the minimum acceptable diameter (reference letter dated May 9,1984). Their conservative calculations performed for Duke Power's Oconee Nuclear Station conclude that, "With 19 studs at a diameter of 3.43 inches, the minimum acceptable diameter of the 20th stud would be 3.20 inches...." Only one stud on "C" RCP had a diameter of less than 3.43 inches at last measurement in May 1988 (stud No. 3 measured 3.415 inches); the remaining studs measured greater than 3.8 inches in diameter (with the exception of affected studs No. 9 and 10). Based on the existing methodology, the stud diameters of the affected studs would be measured and compared to the minimum acceptance criteria of 3.20 inches. If the diameters exceed 3.20 inches, then the studs can adequately perform their safety function. , | ACCEPTANCE CRITERIA 0 Stud diameter greater than 3.20 inches O Leak repaired The existing analysis of acceptable stud diameters performed by the RCP manufacturer (Bingham-Willamette Company) has established 3.20 inches as the minimum acceptable diameter (reference {{letter dated|date=May 9, 1984|text=letter dated May 9,1984}}). Their conservative calculations performed for Duke Power's Oconee Nuclear Station conclude that, "With 19 studs at a diameter of 3.43 inches, the minimum acceptable diameter of the 20th stud would be 3.20 inches...." Only one stud on "C" RCP had a diameter of less than 3.43 inches at last measurement in May 1988 (stud No. 3 measured 3.415 inches); the remaining studs measured greater than 3.8 inches in diameter (with the exception of affected studs No. 9 and 10). Based on the existing methodology, the stud diameters of the affected studs would be measured and compared to the minimum acceptance criteria of 3.20 inches. If the diameters exceed 3.20 inches, then the studs can adequately perform their safety function. , | ||
i j | i j | ||
* Rancho Seco has contracted B&W to update the minimum acceptable stud diameter based on computer modeling analysis techniques developed in , | * Rancho Seco has contracted B&W to update the minimum acceptable stud diameter based on computer modeling analysis techniques developed in , | ||
Latest revision as of 15:55, 9 December 2021
| ML20195C026 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 06/15/1988 |
| From: | Andognini G SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| GCA-88-385, NUDOCS 8806220091 | |
| Download: ML20195C026 (15) | |
Text
.
(m) SMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT C 6201 S Street. P.O. Box 15830. Sacramento CA 958521830.1916) 452 32't AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA VUN161900 GCA 88-385 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Station Pl-137 Washington, D.C. 20555 Docket No. 50-312 Rancho Seco Nuclear Generating Station License No. DPR-54 REACTOR COOLANT PUMP (RCP) LEAKAGE ACTION PLAN f
Reference:
Andognini to Crutchfield letter dated May 17, 1988, RCP Stud Integrity
Dear Sir:
As committed in the referenced correspondence, the District I hereby submits the action plan addressing "C" RCP gasket leakage and RCP stud integrity. The action plan contains acceptance criteria for continued use of the "C" RCP studs and associated schedules and illustrations.
Members of your staff requiring additional information or clarification may contact Steve Crunk at (209) 333-2935, extension 4913.
Sincerely,
/
- ad
. ~~
G. Ca And nini Chief Executive Officer, Nuclear i
1 l
Attachments !
I cc W/atch: J. B. Martin, NRC, Walnut Creek (
A. D'Angelo, NRC, Rancho Seco i I
{
8806220091 DR 880615 ADOCK 05000312 DCD RANCHO SECO NUCLEAR GENERATING STATION O 14440 Twin Cities Road, Herald, CA 95638-9799;(209) 333-2935
ACTION PLAN FOR RANCHO SECO NUCLEAR GENERATING STATION "C" RCP GASKET LEAKAGE l
1 l
i i
ACTION PLAN "C" RCP GASKET LEAKAGE PURPOSE This action plan assures that the "C" RCP studs continue to perform their designed safety function - maintain primary system integrity. Additionally, it assures repair of the leaking "C" RCP gasket.
SCOPE The action plan defines near-term actions to !nspect and evaluate "C" RCP studs. It provides actions to temporarily seal the "C" RCP leakage with sealing compound. It provides actions to replace RCP studs if evaluations conclude they do not meet established acceptance criteria. The action plan defines long-term action to repair the leaking RCP gasket.
BACKGROUND The "C" RCP is currently operating with a gasket leak in the vicinity of the No. 9 stud. Boric acid crystals which accumulated around studs No. 8, 9. and 10 over the two-month period from March 9 to May 9,1988, resulted in approximately 0.14-inch wastage of the No. 9 and 10 studs. A subsequent engineering evaluation of this condition concluded it acceptable until November 1988, based on predicted corrosion rates and existing acceptance criteria on minimum stud thickness. Rancho Seco has scheduled a re-inspection ,
and re-evaluation on or before July 15, 1988 l Babcock and Wilcox (B&W), contracted by the B&W Owners Group, analyzed stud i failure on the RCP main closure due to observed corrosion wastage in pump l closure studs in several plants. B&W chose the Rancho Seco RCPs for modeling l purposes. The resulting analysis showed that a loss of seven studs would not I lead to catastrophic failure of the pump closure. Total failure of five studs would result in a minimum calculated leaking of 4.8 gpm, well above the minimum detectable leakage threshold and above the acceptable Technical Specification value. The maximum calculated leakage resulting from the total failure of five studs is 100 gpm, well within the capability of the makeup pump (rated at 300 gpm). (Reference BAW-1892P, May 1986 Steam Cenerator Manway and RCP Bolted Closure Evaluation.)
Attachment I is a cross-section of the Bingham RCP. Attachment II is the RCP assembly detail drawing. Attachment III is the RCP pump and seal parts list.
Attachment IV provides plan and elevation views of the RCP seal piping and stud locations.
1 J/
NEAR-TERM ACTIONS A planned maintenance outage, designated P02, is scheduled to begin prior to July 15,1988, to accomplish the following items:
- 1. Remove and quantify the boric acid crystals that have accumulated around the RCP studs.
- 2. Measure the thickness of the RCP studs exposed to boric acid deposits.
- 3. Evaluate the continued use of RCP studs based on pre-established acceptance criteria (addressed below).
- 5. Replace degraded studs, if any, which do not pass acceptance criteria for continued operation.
3 Attachment Y is the tentative schedule for the "C" RCP leak repair during the July outage.
ACCEPTANCE CRITERIA 0 Stud diameter greater than 3.20 inches O Leak repaired The existing analysis of acceptable stud diameters performed by the RCP manufacturer (Bingham-Willamette Company) has established 3.20 inches as the minimum acceptable diameter (reference letter dated May 9,1984). Their conservative calculations performed for Duke Power's Oconee Nuclear Station conclude that, "With 19 studs at a diameter of 3.43 inches, the minimum acceptable diameter of the 20th stud would be 3.20 inches...." Only one stud on "C" RCP had a diameter of less than 3.43 inches at last measurement in May 1988 (stud No. 3 measured 3.415 inches); the remaining studs measured greater than 3.8 inches in diameter (with the exception of affected studs No. 9 and 10). Based on the existing methodology, the stud diameters of the affected studs would be measured and compared to the minimum acceptance criteria of 3.20 inches. If the diameters exceed 3.20 inches, then the studs can adequately perform their safety function. ,
i j
- Rancho Seco has contracted B&W to update the minimum acceptable stud diameter based on computer modeling analysis techniques developed in ,
conjunction with BAW-1892P preparation. The updated analysis is not projected to be complete until approximately July 1,1988, but it is <
anticipated that the resulting value will be less than 3.20 inches. If i satisf actorily completed, reviewed and documented prior to the outage, the
! B&W updated acceptance criteria will be used for evaluations performed i during the outage.
2
LONG TERM ACTICNS The long-term actions planned to address the effects of boric acid on the "C" RCP studs include continued monitoring in accordance with surveillance procedures. When the punp is disassembled during the Cycle 8 refueling outage, the District will replace the RCP gasket and repair the gasket surfaces. This restoration work will involve removing the leak compound and replacing all eroded studs. The Long Range Schedule Program will schedule "C" RCP disassembly. The long-term task to repair the gasket will be a major project requiring approximately 6000 manhours of District and contract labor.
1 i
3
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RANCHO SECO RCP 'C' LEAK REPAIR Jul 13, 1988 . J uly 1988 . 11 - Mon 12 - Tue 13 - Wed 14 - Thu 15 - Frl 16 - Sat 17 - Sun 10 - Mon 19 - Tue 2D - Wed 21 - Thu 22 - Fri 23 - Sat 24 - Sun . MtDIS MIDIS MfDis MIDIS l.MIDtS MIDIS MIDtS MIDIS MIDIS MIDIS MtDIS MIDIS MIDtS MIDIS , Run Rooctor Building Coolers .
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Preporotion/ Planning M.15. WRs. RWP, CUPS. Ports, Tools t Yes - Cooldown! to CSD ~ Rooctor ! Shutdown 10-8 hmps -. i
>O I'nitial Containmenf Ent .- -
- - Remove; Seal Pipe Remove Boroni C-RCP i
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'. ; i Yes - R.B. Closecut R.B. Closecut 1
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