ML20065H456

Final Deficiency Rept Re Nonconforming Transamerica Delaval Standby Diesel Generator ASME Section Iii,Class 3,piping Welds.Initially Reported on 820329.Weld Insp & Required Repair/Rework Will Be Completed by 830401

ML20065H456
Person / Time
Site:	Perry
Issue date:	09/24/1982
From:	Davidson D CLEVELAND ELECTRIC ILLUMINATING CO., TENNESSEE VALLEY AUTHORITY
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20065H458	List: ML20065H456
References
10CFR-050.55E, 10CFR-50.55E, RDC-52(82), NUDOCS 8210050132
Download: ML20065H456 (2)

Text

,

l THE CLEVELAND ELECTRIC ILLUMIN ATING COMPANY P O. BOX 5000 m CLEVEL AND, OHIO 44101 e TELEPHONE (216) 622-9800 m ILLUMINATING BLOG e 55 PUBLIC SOUARE Serving The Best Location :n the Nation Da!wyn R. Davidson VICE PRESIDENT SYSTEM ENGINEERING AND CONSTRUCTION September 24, 1982 Mr. James G. Keppler Regional Administrator, Region III Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 RE: Perry Nuclear Power Plant Docket Nos. 50-440; 50-441 Standby Diesel Generator ASME Code Piping Welds [RDC 52(82)]

Dear Mr. Keppler:

This letter will serve as the Final Report as required by 10CFR50.55(e) on the potential significant deficiency concerning Transamerica Delaval Standby Diesel Generator ASME Section III, Class 3, piping. This matter was firs t reported by Mr. E. Riley of The Cleveland Electric Illuminating Company to Mr. J. Nelsler of your of fice, on March 29, 1982. An Interim Report was then submitted on April 28, 1982.

This report contains a description of the deficiency, an analysis of safety implication, and corrective action.

DESCRIPTION OF DEFICIENCY Transamerica Delaval, Incorporated, is supplying four (4) diesel generator units, Model DSRV16, to be used as a standby power source for the Perry Nuclear Power Plant. During a pre-ins talla tion inspection program conducted by the ins talling contractor, diesel generator jacke t water pipe 02.717.02DV/

75051 was found to have a fillet veld overlap which violated the surf ace condition of welds for ASME Section III Class 3 pipe. In addition, lube oil pipe 02.717.01TH/75051 had weld reinforcement which violated ASPIE Section III Class 3 requirements for veld reinforcement. These nonconfort.ances were documented on site nonconformance report PO 39-0477. Upon the detection of these two nonconforming welds, a sampling of all code piping welds was initiated. ,

This inspection consisted of approximately 20 pipes (100 welds) and approximately l 10 welds were nonconforming.

8210050132 820924

_ IE37 PDR ADOCK 05000440 S PDR S6P D 0 882

, l

. Mr. James G. Kspplsr SIPtember 24, 1982

. ANALYSIS OF SAFETY IMPLICATIONS Failure of any welds in.this piping could result in diesel generator unavail-ability. However, fallure of these welds is unlikely due to the low operating pressures of the systems and the large design margin used in system design.

CORRECTIVE ACTION As a result of the identified deficiencies, an inspection of all ASME code pipe supplied by Delaval was initiated. At this time, weld inspection and any required repair and/or rework has been completed for nearly all code piping on one engine and approximately twenty-five percent for a second engine. It is estimated that all corrective action will now be completed by April 1,1983.

If you have any questions, do not hesitate to contact us.

Sincerely, sk b Dalwynw. Davidson ,

Vice President System Engineering and Construction DRD:pab cc: Mr. M. L. Gildner NRC Site Office Director j Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 U.S. Nuclear Regulatory Commission c/o Document Management Branch Washington, D.C. 20555 a

i i

l

)

A I

l l

l temperature, compare it to a previous reading-to determine the heatup rate, and store the present information for subsequent comparisons. Of course, a pool temperature monitoring system requires a thorough temperature measurements program to correlate pool bulk mean temperatures to indicated temperatures on distributed local sensors. A microprocessor is a logical integrating device for such a situation.

2.7 Add Suppression Pool Temperature Trip and Change Reactor Low Water Level Trip Setpoint to TAF (Option 7)

The seventh option adds a suppression pool high temperature trip in parallel with the high drywell pressuza trip and lowers the low reactor cater level trip setpoint to the top o f the active fuel. For this option the ADS would be initiated by either high drywell pressure or an elevated suppression pool temperature. The reactor low water level initiation setpoint is also lowered to TAF. The remainder o f the logic for this alternative is unchanged from the current design. This concept becomes more complex and is not treated further.

2.8 Add Manual ADS Inhibit Switch (Option 8)

The eight option adds a manual switch to the present logic which allows the operator to prevent (inhibit) automatic ADS initiation. As previously discussed in Section 2.2, the manual inhibit feature assists the operator in the execution of certain steps in some EPGs. To inhibit the ADS with the present logic the operator must repetitiously reset the two-minute delay timer or lock out all of the low pressure ECCS pumps.

With the implementation of the symptom oriented EPGs this option satisfies

. _ _ _ _ _ - - - _ - _ _ - _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ - _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ - _ _ _ - _ _ - - - - _ _ _ _ _ _ - - _ - _ _ _ _ _