ML18038B512

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Forwards Update to for Sequoyah Nuclear Plant Unit 2 as Requested in Nrc/Tva 880429 Meeting Re Performance Testing of Reactor Relief & Safety Valves
ML18038B512
Person / Time
Site: Browns Ferry, Sequoyah  Tennessee Valley Authority icon.png
Issue date: 06/24/1988
From: Gridley R
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18038B503 List:
References
NUDOCS 9511080203
Download: ML18038B512 (4)


Text

5N 157B Lookout Place JUICE 24 1%9 8+

pe U.S. Nuclear Regulatory Commission ATTN:

Document Control Desk Vashington, D.C.

20555 Gentlemen:

Zn the Hatter of Tennessee Valley Authority SEQUOYAH NUCLEAR PLANT (SQN)

SAFETY VALVES

)

Docket Nos. 50-327

)

50-328

- PERFORMANCE TESTING OF REACTOR ELK~~

AND

Reference:

TVA letter from J. A. Domer to E. Adensam, NRC, dated March 18, 1985 Enclosed is an update to the referenced lee.cer for SQN unit 2 as requested in the NRC/TVA April 29, 1988 meetin TVA vill evaluate t eva ua e

he effectiveness for unit 2 through compliance vith the technical specifications for'eactor coolant t

1 aka an sys em e

ge.

Enclosure cc:

See page 2

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Zf you have any ques ions, please telephone Kathy S. thitaker at (615) 870-7748.

Very truly yours, maize~

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TENNESSEE VALLEY AUTHORIT J'Ju 3 ~ V..<

Original Signum >7 R.L. Gr'dhX R. Cridiey, Director Nuclear Licensing and

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i aegulatary AEEaic ~,i.=.. m i

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ENCLOSURE PERFORCE TESTXHC OF.REACTOR RELXEF AND SAFETY VALVES SEQUOYAH (SQM) UNIT 2 The original design foc SQN included water-filled loop seals on bith the povec'-operated relief valves (PORV) and the safety/relief valves

(':./RV).

Reanalysis of the discharging piping loads after completion of the El esearch Institute (EPRI) relief valve test program indicated that n

o e

ectrxc caused b

th y

e discharge of the loop seal slug vere excessive.

TV/L decided to xca e

a loads eliminate the PORV loop seals (by rerouting of the piping), to drain the S/RV loop seals, and to install steam trim in the S/RVs.

The e modifications were implemented on unit 1 ducing the refueling outage aftec'uel cycle 2.

Subsequent to this modification on unit 1, high S/RV tail pipe temperatures vere observed that vere interpceted to indicate valve leakage past the seat.

To eliminate the leakage, TVA ceestablished the S/RV loop seals.

Aftec'valuating the options available to resolve the issue.

TVA implemented the changes (removing the PORV loop seals, d~ing the S/RV loop seals, and installing the steam trim in the S/RVs) on unit 2 during the refueling outage after fuel cycle 2.

modifications and additions vere mad t

th d

the discharge piping to reduce the S/RV flange loads in order to ceduce the likelihood of valve seat leakage.

As a contingency, modifications were installed to allow operation with a heated loop seal to reduce the t d

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e ce e magna ude s ug xscharge pxpxng loads, heat t:.:ing and insulation were installed on the loop seal to maintain elevated fluid temperatures; and supports on the discharge piping vere added or modified to accommodate t.".e s1ug discharge loads.

The piping was qualified to loads predicted with the RELAPSIHO01 d

XP computec'odes.

Seat leakage during startup necessitated the cefilling an of the loop seals.

Xn August 1985, SQM units 1 and 2 entered ex ended shutdowns.

Unit 1 vas nearing completion of the refueling outage at the end of fuel cycle 3, and unit 2 vas in fuel cycle 3.

Duc'ing the extended shutdown, water trim vas installed in the unit 1 and unit 2 S/RVs in keeping vith the heated loop seal operation.

During heatup of unit 2 af tee the extended

outage, S/RV seat leakage and pcoblems vith the loop seal temperature control occurred.

TVA then decided to reevaluate the options.

TVA nov plans to operate unit 2 vith drained loop seals and steam trim in the S/R s.

The piping vas designed for a heated loop seal discharge and is moce than adeouate for the steam discharge.

The piping ha" also b

a so een rigorously qualified to loads generated vith RELAP5/MOD1 and REPXPK for discharge of.

steam fcom the S/RVs (without PORV actuation) and foc steam discharge from the PORVs.

To eliminate the pcoblems with valve seat leakage, supports have been modified to reduce the S/RV flange loads to vithin those specified by Crosby Valve and Gauge Company (the valve manufacturer).

The valves have also been serviced and tested by Pyle Laboratories before installation.

1'