View source for 05000336/LER-1984-005-01, :on 840128,while Shutdown for Refueling & Performing Type B & C Penetration Local Leak Rate Tests, Combined Leakage Rate Found in Excess of Tech Spec.Caused by Mechanical Deficiencies

{{Adams
| number = ML20206F399
| issue date = 06/19/1986
| title = :on 840128,while Shutdown for Refueling & Performing Type B & C Penetration Local Leak Rate Tests, Combined Leakage Rate Found in Excess of Tech Spec.Caused by Mechanical Deficiencies
| author name = Romberg W, Stadwick S
| author affiliation = NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
| addressee name = 
| addressee affiliation = NRC OFFICE OF ADMINISTRATION (ADM)
| docket = 05000336
| license number = 
| contact person = 
| document report number = LER-84-005-01, LER-84-5-1, MP-9195, TAC-60646, NUDOCS 8606240454
| document type = LICENSEE EVENT REPORT (SEE ALSO AO RO), TEXT-SAFETY REPORT
| page count = 3
| project = TAC:60646
| stage = Other
}}
{{LER
| Title = :on 840128,while Shutdown for Refueling & Performing Type B & C Penetration Local Leak Rate Tests, Combined Leakage Rate Found in Excess of Tech Spec.Caused by Mechanical Deficiencies
| Plant = 
| Reporting criterion = 
| Power level = 
| Mode = 
| Docket = 05000336
| LER year = 1984
| LER number = 5
| LER revision = 1
| Event date = 
| Report date = 
| ENS = 
| abstract = 
}}

=text=
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" NR Form 3est u S. NUCLEfA kEtuLaTORY COMMISSION e
APPROVED OMS NO 3150-e10.
LICENSEE EVENT REPORT (LER)
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Containment Local Leak Rate Limits Exceeded EVENT DATE Ill LER NuMSER (6)
REPORT DATE (7)
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NAME TELEPHONE NL'M8ER Stephen L. Stadnick
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==CAUSE==
SYSTEV COMPONENT

==CAUSE==
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ABSTR ACT (Lest m r400 speess. e e, sporeseem'r Mreea ssgse sosce typeenrwa hees/ 046 While performing Type B and C, Containment penetration Local Leak Rate Tests during refueling, a combined leakage rate in excess of that allowed by Technical Specification 3.6.1.2.b. was noted. Additionally the combined secondary containment bypass leakage rate was in excess of that allowed by 3.6.1.2.c.
Several closed cooling water isolation valves and both containment sump isolation valves were found to have various mechanical deficiencies resulting in excess leakage rates.
Repairs to these valves were affected. All deficiencies were corrected and the affected penetrations retested satisfactorily.
The plant remained in Mode 5 until both leakage rates were restored to within j
the limits specified in Technical Specification 3.6.1.2.b and 3.6.1.2.c.
This report was submitted more than 30 days past the date of the actual event due to an administrative oversight.
The actual Local Leak Rate Tests and repairs to associated valves were performed prior to the Integrated Leak Rate Testing conducted on December 23, 1983, but the Local Leak Rate Test data was not reviewed until the listed event date (1/28/84). This update report is being submitted to clarify the actual sequence of events.
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NRC Fore 366A U 5. NUCLEAR RETULATORY COMMISSION LICENSEE EVENT REPOAT (LER) TEXT CONTINUATITIN urnoveo oms No mo-oio.
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While shutdown for refueling and performing Type B and C penetration Local Leakrate Tests in accordance with Surveillance Procedure 2605C and 2605D, respectively, combined leakage rates in excess of those allowed by Technical Specification Sections 3.6.1.2.b. and 3.6.1.2.c. were noted.
Investigations revealed that closed cooling water isolation valves for penetrations 25/30, 26/31, 27/32, and 28/33 and containment sump isolation valves for penetration 14 were leaking excessively due to mechanical deficiencies.
The combined leakage rate for Type B and C penetrations exceeded the Technical Specification 3.6.1.2.b. limit, actual leakage was 1.339%/ day.
The combined leakage rate for secondary containment bypass penetrations exceeded the 3.6.1.2.c. limit, actual leakage was 0.062118%/ day.
Corrective action included the repair of all isolation valves for the above penetrations. The penetrations were retested and found to have acceptable leak rates.
In addition to the above corrective action repairs and retests, a Reactor Building Containment Integrated Leakrate Test was performed and met the requirements of Technical Specification 3.6.1.2.a.
Further information will be provided in that report.
Similar LERs 79-034/03L-0 80-032/03L-0 82-006/03L-0 Valve Data 2-RB-28.1A, 28.1B, 28.1C, 28.1D 2-RB-28.3A, 28.3B, 28.3C, 28.30 10 inch butterfly, Fisher type 9222 with Bettis CB-525-SR-80 Actuators 2-RB 28.2A, 28.2B, 28.2C, 28.2D 6 inch butterfly, Fisher type 9222 with Bettis CB-SR-80 Actuators 2 SPP 16.1 and 16.2 3 inch globe, Masoneilan with three way solenoid valve operators.
This update report is being submitted to clarify the sequence of events as they occurred and were subsequently reported. The actual Local Leak Rate Tests and repairs to the associated valves were performed on approximately 12/20/83, just prior to the performance of the Integrated Leak Rate Test.
The Local Leak Rate Test data was not reviewed until the listed event date when it was determined that the penetrations noted above had failed to meet "as found" acceptance criteria, resulting in this original report. Additionally, the 1985 refueling shutdown included both LLRT and ILRT and the results were promptly reviewed and reported.
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==Reference:==
Facility Operating License No. DPR-65 Docket No. 50-336 Reportable Occurrence R0 50-336/84-005-01 Gentlemen:
This letter forwards the Licensee Event Report 84-005-01 concerning Containment Local Leakage Rates limits exceeded.
Yours truly, NORTHEAST NUCLEAR ENERGY COMPANY
/
h/
Wayne D.
erg Station Superintendent Millstone Nuclear Power Station WDR/SLS:cjh

==Attachment:==
LER R0 50-336/84-005-01 cc:
Dr. T. E. Murley, Region 1 Y'k, t
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