ML20099B890
| ML20099B890 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 07/28/1992 |
| From: | Mccarthy D CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLS-92-192, TAC-M81881, NUDOCS 9208030138 | |
| Download: ML20099B890 (7) | |
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i CP&L Catohna Power a 1,lght Company
'JUL 281992 SERIAL: NLS 92192 United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 & 50-324/ LICENSE NOS. DPR 71 & DPR 62 EMERGENCY DIESEL GENERATOR OPERABILITY (NRC TAC NO. M81881)
Gentlemen:.
The purpose of this letter is to respond to issues raised by the NRC Staff with regard to the operational readiness of Emergency Diesel Generator Number 3. In a letter dated April 21,1992, the Nuclear Regulatory Commission staff provided the results of their review and evaluation of information concerning the adjustment of Intake valves for emergency diesel generator number 3.
In the letter, the staff concluded that EDG 3 la currently operational and capable of performing its design function. However, the staff ralsed several issues and recommended certain inspcetion actions, The purpose of this letter is to provide information concerning measures taken to address the NRC staff issues raised in the April 21,1932 letter. Based on the information provided herein, CPSL considers this issue to be closed.
Please refer any questlons regarding this submittal to Mr. W. R. Murray at (919) 546-4601.
Yours very truly, N
D. C. McCarthy Manager I:uclear Licensinp Section WRM/wrm (edo-31tr.002)
Enclosure -
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Mr. S. D. Ebnater Mr. R. H. Lo.
Mr. R. L. Prevatte.
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i ENCLOSURE 1 E.UNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCXET NOS. 50 325 & 50 324 OPERATING LICENSE NOS. DPR-71 & DPR 62 EMERGENCY DIESEL GENERATOR OPERABILITY (NRC TAC NO. 81881)
INTRODUCTION 1
This information docun ents Carolina Power & Light Company's response to the NRC letter dated April 2T,1992 concerning the operability of emergency diesel generator number 3 at Brunswick Steam Electdc Plant. In the April 21/1992 letter, the NRC staff indicated that the information presented by UnL had not justified operating the diesel engines above an originally recommended vendor tempereture li< nit of 775'F for cylinder exhaust. The NRC further indicated that if no other L
justifiable dor,e%ation is available, then CP&L shculd pursue tha four actions listed below or propose alterr.ves to ensure that no damage has oce, *ed to EDG 3 and to ensure the long term operability
.he remaining EDGs:
Calibrate all EDG pyrometers.
2.
Review operating logs on all DG's installed at BSEP and identify all cylinders with readings in excess of 775'F.
3.
Select the cylinder that was subjected to the highest temperature exceeding the 775'F limit in each EDG and conduct an inspection on this cylinder using a baroscope or, preferably, a video probe to detect the possibility of valve damage.
Access should bn ths:1ah the injector opening if pcssible; however, in the event a clear view is not attainable, it is recommended that the exhaust header be removed to inspect the valves through the exhaust port. These inspections should be completed on EDG-3 and three remaining EDGs at the earliest opportunity, but no later than the next refueling outage. Any unusual findings shou!d be reported to NRC.
4.
Balance all engines to meet as closely as feasible, temperature and firing pressure
-limits established in the Technical Manual at 100% load. Test data, including the cylinder exhaust temperatures, taken during the operability surveillance test after balancing of engines should be submitted to NRC for review.
RESPONSE
As discussed with the NRC Staff on June 11,1992, Carolina Power & Light Company has obtained from the current Nordberg vendor, Hatch and Kirk, additional information justifying an operating temperature of 940'F for the diesels, in preparation of CP&L's [[letter::05000325/LER-1991-027, :on 911105,hydraulic Control Unit 34-19 Declared Inoperable When CRD Accumulator Low Pressure/High Level Alarm Received.Caused by Decrease in Reactor Temp. Accumulators Recharged & TS Change Underway|November 27,1991 letter]] to the NRC Staff, the Assistant Chief Engineer for Nordberg was consulted. He reviewed the compnnents utilized in the original design of the diesel engines and concluded that the limit of 940'F was l'
acceptable. Additionally, the fact that the diesels were deliverra from the factory as acceptable I
with temperatures above 800*F during factory testing was notsd. The Nordberg engineer war questioned as to why the technical manual stated a limit of 775'F if the design limit was higher.
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4 He stated that the values shown in the technical manual were expected operating ranges for our diesets, not design limits. The safety evaluation enclosed with the April 21,1992 NRC staff letter also expressed concern over an additional temperature, the turbocharger inlet temperature limit.
On the same list of expected operating rco;,es, this ternperature is listed as exoected from 940'F to 1020*F. Later in the technical manual, the design limit is given as 670'C (1238'FL This is provided in the BBC VTR 500 Turbocharger technical manual enclosed as a portion of the Nordberg
- manual, in order to further the position that 940'F was acceptable as a design limit for diesel cyhnder exhaust, the current Nordberg vendor, Hatch and Kirk, was consulted. Mr. Bill Steele of the engineering group of that company provided the attached response dated April 22,1992 (Attachment 1h Withniatch and Kirk's concurrence, CP&L will update the Nordbnto technical manual to reflect a cylinder exhaust limit of 940 'F.
ADDITIONAL ACTIONS In addition to justifying the increased operating temperature for the diesels, Carolina Power & Light Company has implemented or is in the process of implementing the actions outlined by the NRC in i
the April 21,1992 letter. These are summarized below:
Action 1:
Calibrate all EDG ovrometem C1rolina Power & Light Company has completed calibration of the cylinder exhaust pyrometers and some data has been taken in preparation for balancing the diesels.
Action 2:
Review ooeratino loas on all DG's installed at BSEP and identify all cylinders with Igadj. nan in extgjip of 775'F.
n Dased on the Hatch and Kirk documentation justifying an operat:ng temperature of t
l 940*F for the diesels, CP&L reviewed the operating logs on the four diesels and identified those cylinders that had experienced operating temperatures in excess of the 9400F limit.
Action 3:
Select the cylinder tMt was sublected to the hiahest temoerature exagedinu thg 775'F fimit in each eDG and conduct on insoection on this cylinder usinn a haroscoes or creferabtv. a video orobe to detect the oossibility of valve damace.
LLecess should be throuah the inlector onenina if oossible; howevmin the event a glear view is not attainable. it is recommended that the exhaust boader be removed 10 inspect the valves throuah the exhaust oort. These insoections should bg ggmoleted on EDG 3 and three remainina EDGs at the earliest onoortunity. but no later than the next refuelina outane. Any unuseat findinas sbatM be reoorted 1
to NRC.
L Despite this assurance from Hatch and Kirk that exhaust temperatures in excess of l
7750F would not damage the Brunswick Plant diesel engines, a review of %e past l
cylinder exhaust temperatures was conducted. Following that review the cylinders whSh had experienced the highest temperaturec in excess of 940*F were
- inspectnd' These cylinders were identified on emergency diesel generators number 2 and 3. The cylinders inspected had experienced ths highest temperatures recorded for.all site diesels for any single diesel run as well is the highest routine temperatures. Mr. Chuck Reynolds, Field Service Manager for Hatch and Kirk was El 2 l$
present for these inspections. The investigation consisted of borescopic and video probe inspections of the valve seats, cylinder liner, and visible intelnal head areas.
No damage associated with high temperature operation was noted. A recording of the video probe inspection was made.
j Action 4:
Balance all enoines to meet as closelv as feasible, temoerature afd firina oressure lim [ts established in the Technical Menual at 100% load. Test data, includino the gvlinder exhaust temperatures. taken durino the ooerability surveillance test after balancino of enoines should be submitted to NPC for review. ik a copy of the cylinder exhaust temperatures requested by the NRC staff for dieselt number 1 and 4.
Based on tree anticipated receipt of necessary parts, CP&L plans to replace the cylinder fuel pumps and injectors on diesels number 1 and 2 during the current
' Brunswick Plant outage. The Company intends to replace the cylirider fuel pumps and fuel injectors for diesels number 3 and 4 as soon as parts are available and plant operating conditions allow (this work in anticipated to be completed during the Unit 2 Reload 10 outage, currently scheduled for Fall 1993). A balancing of each diesel will be performed when the new components are installed. Balancing that can be performed prior to obtaining and Installing the replacement components will
. be accomplished in conjunction with other planned diesel maintenance and testing.
I CONCLUSIONS Tne content of the plans and actions described above were discussed with the NRC staff during a.
telephone call on June 11,1992. During that conversation, CP&L's understanding was that the NRC staff c: reed with our conclusion that the 940 *F limit is acceptable considering the additional Input from Hatch and Kirk. Additionally, the scheduling for additional action was also acceptable.
The Company will provide the temperature data from diesel generators number 2 and 3 to the NRR Project Manager after completion of a thorough balancing.1herefore, based on the information provided above, CP&L considers this issue to be closed.
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'th, ATTACHMENT 1 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 e
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I Hatch and Kirk Response dated April 22,1992 o
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HHHH HHKK PMHK ENQ!NE PARTS SPECIALISTD HHHH HHKK Kk.tK HHHHHHHHKKKKKK DATE: APR. 22 I'd 9 2 HHHHHHHHKKKKKK HHHH HHKK KKKK TO: BILL STACMHOUSE HHHH HHKK KKKK HHHH HHKK KKKK COMPANYI CP&L FAX NUMBER: (919)457-2155 FROM: BILL STEELE TOTAL NUMBER OF #AGEB FAXEDs 1
MESSAGE
- h1LL, IN REVIEW OF YOUR ANSWERS TO THE NRC QUESTIONG CONCERNING THE CYLINDER EXHAtf3T TEMPERATURES OF THE DIEEEL GENERA'3R UNITS, 1 AGREE WITH O PNGING THE MAXIMUM TEMPERATURE FROM 775 DEGREES FARENHEI'.
') 940 DEGREES FARENHEIT.
CHANGING THE MAXIMUM CYLINDER EXHAUST TEMPERATURE WILL NOT AFFECT THE PERFORMANCE OF THE DIESEL GDJERATOR UNf T.
BEBT REGARDS.
PURCHASING APR 2 21992 %
BILL STEELE RNOR./ MFG.
IF YOU DO NOT RECEIVE THE TOTAL NUMBER OF PAGES BEING SENT PLEASE CALL (7tal926-977A.
l 601 McFARLAND - HOUSTON, TEXA8 77011
ATTACHMENT 2 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 Diesel Generator Number 1 3500 kW Test Run May 16,1992 blindef Temoerature oF 1R 750 2R 745 3R 745 4R 770 SR 730 6R 730 7R 705 BR 750 1L 700 2L 730 3L 765 4L 695 SL 745 6L 740 7L 730 BL 760 Dioso' Generator Number 4 3500 kW Test Run May 22,1992 Cvlinder Temperature *F 1R 780 2R 700 3R 780 4R 770 SR 760 6R 750 7R 770 BR 800 1L 760 2L 750 3L 740 4L 750 SL 740 6L 780 7L 760 8L 760 i
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