ML20210K167

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Discusses 860402 Telcon W/B Pollard of Ucs Re IE Info Notice 86-005, Main Steam Safety Valve Test Failures & Ring Setting Adjustment
ML20210K167
Person / Time
Issue date: 04/14/1986
From: Wegner M
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To: Baer R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
Shared Package
ML20210K171 List:
References
FOIA-86-266 IEIN-86-005, IEIN-86-5, NUDOCS 8604170629
Download: ML20210K167 (6)


Text

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  • A MEMORANDUM FOR: Robert L. Baer, Chief

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Office of Inspection and Enforcement THRU: James E. Wigginton, Acting Chief, Section B Engineering and Generic Comunications Branc Division of Emergency Preparedness and Engineering Response Office of Inspection and Enforcement FROM: Mary S. Wegner, Nuclear Engineer Engineering and Generic Comunications Branch Division of Emergency Preparedness and Engineering Response

  • Office of Inspection and Enforcement

SUBJECT:

TELEPHONE COMMUNICATION OF 04/02/86 FROM B0B POLLARD, UCS At 1:45 p.m. on April 2,1986, I received a call from Mr. Bob Pollard of the Union of Concerned Scientists about Information Notice 86-05, " Main Steam Safety Valve Test Failures and Ring Setting Adjustments." He asked if any additional comunications had been issued by NRC on the subject. I replied that I knew of none. I informed him that I had received a copy of the request for prioritization of the Generic Issue: " Main Steam Safety Valve Reliability" on the previous day. He basically wanted to know what further action NRC would be taking and I informed him that such action would be dependent upon identify-ing safety concerns and the outcome of the prioritization. I also mentioned that I had been tracking other reliability concerns such as failure to open, failure to reseat, and set point drift and that I was composing an information notice on that.

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Robert Baer Mr. Pollard asked if NRC had done any valve testing. I replied that I knew of none which may have been done or planned. I said that I had been at Wyle Lab recently and the test rig for full size-full flow testing had not been used recently so I did not think NRC had done any tests. He further inquired about the tests which were performed in lieu of full size-full flow testing. I said that the valve size was on the order of 2 to 4 inches and they were prototype valves rather than each and every valve in the plant. The licensee would use the data on the prototypical valve in an analysis to determine the applicabil-ity of the tests to the valves actually used in the piant.

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  • Sscbrcok Unit 1 Licossoe Tolophoco R: port DN 50-443 ffThelicenseere$ortedapotential50.55(e)deficione concerning Cros y Main Steam Safety Valves. During t stine at Wyle Labs, it was found that the valve disc did not travel its required distance. The problem was attributed to the valve ring valve disc travel was I setting. When achieved. the ringthis At Seabrook washas readjusted the po {ential for affecting a total of 20 Crosby Main Steam Safety Valves. The licensee is j

\ investigating to determine the entent it esists. i Nine Mile Point Unit 12/16 ENS; 12/17 Licensee phone The reactor was shut down at about 5 p.m. on December 16, to DN 50-220 repair an air leak on one of the Backup Scram Solenoid Valves. l i

The esistence of the leak prevented normal surveillance testing l of the scram system at power without risking an actual trip. I Repairs should be completed and the plant returned to power l today (12/17).

I J.A. FitzPatrick 12/14 SRI phone / Plant Shutdown At 6:15 p.m. on 12/14, the licenses commenced a plant shutdown l DN 50-333 to repair the "B" core spray minimum flow valve (a containment isolation valve) which would not shut completely. Followine the sepairs, a reactor startup was commenced at 10:30 p.m. on 12/15 and the generator was synchronized to the grid at 2:10 p.m. on 1

12/16.

MORNING REPORT - REGION II DATE: December 17, 1984 LICENSEE / FACILITY NOTIFICATION / SUBJECT DESCRIPTION OF ITEM OR EVENT Catawba 1 Resident Inspector, Update of December T 1984 report en the Heavy control rod drive mechanism DN: 50-413 12/17 fabrication error, the licensee has completed inspection of the mechanisms and as a result replaced a total of 14 mechanisms. The licensee estimates to be in Mode 5 on 12/20 and to return to 557 degrees F for entry into Mode 2 on 1/7/85. Initial criticality is now planned for 1/10/85. Information only.

McGuire 2 HQS Duty Officer, Reactor / Turbine t rip f rom 1005 power due to t rip of *A" main feed pump en DN: 50-370 12/17 low vacuum and inability of "B" main feed pug to keep up with feed demand.

Reactor tripped on "C" Steam Generator Lo Lo level. Licensee plans to return to power on 12/17. Routine followup.

S2quoyah 1 & 2 Duty Officer, At 4:26 a.m. EST, on 12/15 with Unit 1 at 1001 power and Unit 2 in Mode 3 DNS: 50-327 12/15 a fire occurred on the 8 p$ase current transformer for an outeoing 500Kv 50-328 Transformer line. The fire brigade responded, and the fire was extinguished in about Explosion and fire eight minutes. There were no injuries and no damage to safety-related equipment. Post-fire review indicated that the t ransformer emploded, possibly due to en internal short. Due to the evidence of emplosion, the licensee declared an Unusual Event (UE) at 5:36 a.m. EST, per the emergency plan and secured the UE at 5:39 a.m. The resident inspectors are following the licensee evaluation. Media interest probable. PN issued and State of Tennessee notified.

Duty Officer. At 9:26 a.m. EST, on 12/16, with the unit in Mode 3, a safety injection (SI) 12/16 actuation occurred on low pressurizer pressure. About 30 minutes earlier, Safety Injection operators had identified a primary safety relief valve weeping based on Actuation elevated ta11 pipe temperature. Primary pressure was reduced using sprays to ressat the valve, and the low pressure SI channels were blocked. Prior to

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t Page No. 1 os/1 ves, l .

MAIN' S1E'AM SAFETY VALVE FAILURES FROM 01/01/M TO PRESENT From LERs, 50.72 reports (EOOOO), morning rdports(Mmmdd),

And Preliminary Notifications (PBS-OO).

PLANT LER NO VALVE NO CAUSE MFGR

    • FAILURE TO OPEN CALVERT CLIFFS 2 E2470 DRESSER 1 FAILURE TO OPEN 'IESTING DAVIS-DESSE 84/003 DRESSER 1 FAILURE TO OPEN TRANSIENT NORTH ANNA 2 MO224 CROSBY O FAILURE T O OPEN TESTING SALEM 2 M1212 CROSBY 1 FAILURE TO OPEN TESTING
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  • Subtotal ++

11

    • FAILURE TO RESEAT CRYSTAL RIVER 3 84/010 UNK 3 FAILURE 10 RESEAT TRANSIENT CRYSTAL RIVER 3 E3210 1 FAILURE TO RESEAT TRANSIENT DAVIS-BESSE 84/003 DRESSER 1 FAILURE TO RESEAT TRANSIENT OCONEE 1 E574 UNK 1 FAILURE TO RESEAT TRANSIENT OLONEE 2 E1423 UNK 3 FAILURE 10 RESEAT TRANSIENT TROJAN 84/017 UNKNOWN 1 FAILURE TO RESEAT TRANSIENT
    • Subtotal **

10

    • LEAKING DAVIS-DEGSE P85-06 DRESSER 4 LEAKING TESTING SALEM 2 85/007 CROSBY 1 LEAKING OTHER
    • Subtotal **

k 5

    • SET POINT DRIFT DYRON 1 85/015 DRESSER S SET POINT DRIFT TESTING CALVERT CLIFFS 1 8S/003 DRESSER / SET POINT DRIFT IESTING CALVERT CLIFFS 2 84/004 DRESSER 16 SET POINT DRIFT TESTING FT CALHOUN 84/002 DRESSER 5 SET POINT DRIFT TESTING SUMMER M10/07 DRESSER 10 SET POINT DRIFT TESTING
    • Subtotal **

43

    • SET POINT DRIFT HIGH DEAVER VALLEY 1 84/011 DRESSER 7 SET POINT DRIFT HIGH TESTING CALVERT CLIFFS 2 E2470 DRESSER 10 SET POINT DRIFT HIGH TESTING FARLEY 1 83/004 UNK 1 SET POINT DRIFT HIGH 'IESTING INDIAN POINT 2 86/002 CROSBY 3 SET POINT DRIFT HIGH TESTING PRAIRIE ISLAND 1 85/002 DRESSER 1 SE1 POINT DRIFT HIGH TESTING
    • Subtotal *+

22

    • SE1 POINT DRIFT LOW DEAVER VALLEY 1 84/011 DRESSER 1 SET POINT DR]FT LOW TESTING DAVIS-BESSE P85-86 DRESSER 3 SET POINT DRIFT LOW TESTING SALEM 2 85/007 CROSBY 3 SET POINT DRIFT LOW OTHER

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Page No. 2 of/2 f/6(o I MAIN STEAM SAFETY VALVE FAILURES FROM 01/01/64 TO PRESENT From LERs, 50.72 reports (EOOOO), morning reports (Mmmdd),

And Preliminary Notifications (P85-OO).

PL All T LER NO VALVE NO CAUSE MFGR

  • + Sul-total **

7

    • SPURIOUS OPEf4ING INDIAN POIN1 3 84/003 UNK 1 SPURIOUS OPENING OTHER INDIAN POINT 3 84/001 UNK 1 SPURIOUS OPENING OTHER
    • Subtotal **

2

      • Total ***

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