ML20069D890

From kanterella
Jump to navigation Jump to search
Provides Addl Info Re NUREG-0737,Item II.D.1.2, Relief & Safety Valve Performance. Westinghouse & Crosby Valve Working on Scheme to Optimize Valve Ring Settings.Fluor Power Investigating Effects of Increased Support Loadings
ML20069D890
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 03/15/1983
From: Musolf D
NORTHERN STATES POWER CO.
To:
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM NUDOCS 8303210058
Download: ML20069D890 (2)


Text

'\\

a s s Northem States Power Company 414 Neo8et Man Minneapoks. Minnesota 55401 Telephone (612) 330 5500 March 15, 1983 Director Office of Nuclear Reactor Regulation U S Nuclear Regulatory Commission Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLGI Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Additional Information Related to NUREG-0737 Item II.D.l.2, Relief and Safety Valve Performance Our letters dated July 1, 1982 and July 19, 1982 provided information related to implementation of ?mREG-0737, Item II.D.l.2, at the Prairie Island Nuclear Generating Plant. Our safety and relief valve installation was described and information was provided showing this installation was bounded by the valves and test parameters of the EPRI Safety and Relief Valve Test Program. We noted that work remained in the area of piping and support evaluation and review with Westinghouse and Crosby of the neces.aity of making ring adjustments to the safety valves. The purpose of this letter is to provide updated infor-mation related to these open items.

Unit 1 Piping and Support Evaluatien The Unit 1 thermal hydraulic analysis is complete.

Results show the need for two additional snubbers downstream of the safety valves plus the addition of insulation to loop seals upstream of the safety valves. The insulation was installed during the Unit I refueling outage (Nov-Dec 82). Material, availability prevented installation of the additional snubbers.

Additionally, Fluor Power is investigating the affects of increased support loadings, which resulted from the new West' < ~' use thermal-hydraulic analysis. While major changes to existe-

. orts are not anticipated, undoubtedly some changes will be ret,2' ed.

Work is now underway to identify material or modifications required to accomplish the work at the next refueling (autumn 83).

,Q Unit 2 Piping and Support Evalua tion l

Analytical work is underway at Westinghouse on the thermal-hydraulic analysis.

Fluor is closely monitoring the Westinghouse work to get an early start on design of additional and/or modified supports. Our goal is to install any required modifications during the upcoming Unit 2 refueling (summer 33).

Similar modifications, as were required for Unit 1, are expected for unit 2.

F3032iOO58 830315 PDR ADOCK 05000282 P

PDR

N c

s

\\

NORTHERN STATES POWER COMPANY Director of imR March 15, 1983 Page 2 Safety Valve Adjustments Westinghouse and Crosby Valve are still working on a scheme to optimize valve ring settings. Westinghouse has indicated that agree:nent with Crosby on approach will occur during early 1983.

Outcome of the joint study is unknown at this time.

Please contact us if you have any questions related to our plans and schedule for resolving these remaining issues.

Nus David Musolf Manager - Nuclear Suppgry Services DFCf/bd cc: Regional Administrator-III, NRC NRR Project Manager, NRC Resident Inspector, NRC G Charnoff

.