ML18054A625
| ML18054A625 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 03/30/1989 |
| From: | Smedley R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM TAC-44604, NUDOCS 8904120013 | |
| Download: ML18054A625 (7) | |
Text
{{#Wiki_filter:... consumers Power POW ERi Nii MICHlliAN'S PROliRESS General Offices: 1945 West Parnall Road, Jackson,' Ml 49201 * (517) 788-0550 March 30, 1989 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - \\ NUREG 0737 Ii.D.l, PERFORMANCE TESTING OF RELIEF AND SAFETY VALVES (TAC NO. 44604) - ADDITIONAL INFORMATION NRC letter dated October 20, 1987, requested 10 items of additional information regarding NUREG 0737, Item II.D.l - Performance Testing of Relief and Safety valves. CPC letters dated March 29, 1988 and May 25, 1988 responded to Items 3-10. CPC letter dated September 14, 1988 gave a partial response to Item 1 by providing complete descriptions of the proposed PORVs and Block Valves. The attachment to this letter provides our response to Item 2 and additional information regarding the ~ew PORVs which will be installed before the end of the 1990 refueling outage. The remainder of our response to Item 1 regarding the similarity of the proposed block valves to valves tested by EPRI will be submitted before July 15, 1989. Richard W Smedley Staff Licensing Engineer CC Administrator, Region III, NRC NRC Resident Inspector - Palisades Attachment .:s*~c>4f2c5c>18--a90:3:3o [ '"'L
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OC0389-0106-NL02 ATTACHMENT Consumers Power Company Palisades Plant Docket 50-255 RESPONSE TO 10/20/87 NRC REQUEST FOR ADDITIONAL INFORMATION ITEMS 1 AND 2 March 30, 1989 5 Pages
NRC ITEM NO. 1 RESPONSE TO 10/20/87 NRC REQUEST FOR ADDITIONAL INFORMATION ITEMS 1 AND 2 1 "The licensee stated that the PORV block valves are normally closed during plant operation, but that these valves could be opened during abnormal operat-ing conditions. In the June 12, 1987 submittal to the NRC, Consumers Power stated that new block valves, which are qualified to the requirements of NUREG-0737 Item II.D.l, were being installed in the Palisades Plant, but did not identify the valves or provide any information regarding qualification of the ~alves. Therefore, provide the following information. Manufacturer, model number, size, pressure rating of block valves, and similar information regarding the valve operator. Describe and discuss all similarities and/or any differences between the valves and operators tested in the EPRI program and the plant valves and-operators. Discuss verification of block valves operability over the range of flow, pressure, and temperature conditions the valves are expected to operate over, including verification of the valve operators capability to open and close these valves."
RESPONSE
Although Item 1 only refers to block valves, since we plan to install new PORVs and block valves at the same time we are including information regarding the PORVs in our response. The manufacturer, model number, size, pressure rating, and information regarding the valve operator for both the new PORVs and Block Valves were submitted in the CPCo letter dated September 14, 1988. The following is a discussion of the similarity of the new PORVs to valves test~d in the EPRI program. At the time NUREG 0737 was issued, Target Rock was in negotiation with Babcock and Wilcox (B & W) to supply power operated relief valves (PORV's) to the Midland Nuclear Plant. Therefore, a sample valve (80X-006) was fabricated for EPRI testing. The results of those tests are reported in EPRI Test Report documents (Reference 1). For the Palisades Plant application, Target Rock is supplying a model 88RR-001 valve. It is of the same design as the valve tested in the EPRI program except for size. Drawing 1052020-1 (Enclosure 1) presents a cutaway view of the EPRI test valve. This drawing can be compared to Drawing
- 1071240-5 which shows a cutaway of the Model 88RR-001 (Enclosure 2).
The similarity is quite evident. Both valves have "Y" pattern forged bodies, employ co-axial plungers, single pilot (operating within the main disc) and cross pin linked to permit main disc lifting at zero ~P. Both valves employ stellite to stellite seating surfaces, 410 SS plungers and fixed core materials with austenitic S.S. bonnet tubes. The performance of the Target Rock style PORV is represented by the EPRI Test. OC0389-0106-NL02
~. 2 However, because of the size difference, the 88RR-001 valve currently being fabricated for the Palisades Plant, will undergo an operational test at actual maximum pressure and temperature conditions with a steam flow of approximately 100,000 #/Hr (a limited maximum flow rate, resulting from the limits of the Target Rock test facility.) This will approximate the EPRI performance test and demonstrate that the target valve being supplied to the Palisades Plant is equivalent to that tested by EPRI (except for size). NRC ITEM NO. 2 "Provide the maximum expected backpressure and bending moment for the Palisades PORVs."
RESPONSE
The maximum expected backpressure for the new Palisades PORVs is 1076.9 psia and is postulated to occur if both valves open at 2400 psia. The maximum expected bending moment for the new PROVs is 3500 ft-lbs about an axis which is normal to the direction of flow. (Enclosure 3) The maximum expected backpressure and bending moment for the existing installed PORVs were submitted in the EDS Nuclear Report attached to our December 30, 1982 l,etter. Reference 1 - EPRI Report NP-2628-LD, September, 1982, Safety & Relief Valve Test Report. OC0389-0106-NL02
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