IR 05000309/1979013
| ML19253C535 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 09/26/1979 |
| From: | Caphton D, Rekito W, Tanya Smith NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19253C527 | List: |
| References | |
| 50-309-79-13, NUDOCS 7912060017 | |
| Download: ML19253C535 (5) | |
Text
.
-
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-309/79-13 Docket No. 50-309 License No. DPR-36 Priority
--
Category C
Licensee:
Maine Yankee Atomic Power Comoany 20 Turnpike Rcad Westborough, Massachusetts 01581 Facility Name: Maine Yankea Atomic pnwor Statinn Inspection at: Wiscasset, Maine
/
Inspection conduct
epterber 6-8, 1979 Inspectors:
tb
^
9
'
,
T. H. Snttth, Reactor Inspector date signed
&)&%2b eks/n W. A. Rekito, Reactor Inspector date s'igned date signed
.
.
h va
~V
/9 Approved by:
D.L.Caphton, Chief,NucleafSupportSection
/date' signed No. 1, RO&NS Branch Inspection Summary:
Inspaction on September 6-8,1979 (Report No. 50-309/79-13)
Areas Inspected:
Routine, unannounced inspection by regional inspectors of the Containment Integrated Leak Rate Test (CILRT) and the inservice test program for pumps and valves.
The inspection involved 28 inspector-hours on site by two NRC regional based inspectors.
Results:
No items of noncompliance or deviations were identified.
1506 345 Region I Form 12 (Rev. April 77)
7912060C/f
.
.
DETAILS 1.
Persons Contacted The below listed technical and supervisory level personnel were contacted:
P. Anderson, Staff Assistant to the Plant Superintendent
- C. Frizzle, Assistant Plant Superintendent J. Hebert, Engineering Supervisor A. Pierce, Mechanical Engineer S. Sadosky, Operations QA P. Willoughby, IST Cootdinator E. Wood, Plant Superintendent The inspector also talked with and interviewed several other members of the engineering and operating staffs.
- denotes those present at the exit interview.
2.
Inservice Testing of Pumps and Valves
,
a.
Documents Reviewed Title 10, Code of Federal Regulations, Part 50.55a(g), Inservice
--
Inspection Requirements.
ASME Boiler and Pressure Vessel Code,Section XI, Subsections IWP
--
and IWV, Inservice Testing of Pumps and Valves in Nuclear Power Plants,1974 edition with Summer 1975 Addenda.
Maine Yankee Atomic Power Station Inservice Inspection Program
--
for the period August 28, 1979 to Decemoer 28, 1982, Appendix A, Procedure 3.17.6 (program submittal to NRC).
b.
Scope The inspector reviewed the licensee's ISI program submittal to verify the listing of applicable safety related pumps and valves to be complete and accurate. The inspector also made field verifications of the validity of justifications given for exemption requests from ASME Code requirements.
The ISI program submittal specified a starting date of August 28, 1979, in conformance to 10 CFR 50.55a(g) requirements, but the program was not submitted 90 days prior to the start date as requested by NRR.
1506 346
.
Subsequently, the ISI program submittal has not received a detailed or preliminary review by NRR.
c.
Implementation Schedule At the time of this inspection, the licensee did not have the necessary procedures issued to implement the inservice testing program.
The licensee stated that the implementing test procedures were being developed and would be issued in sufficient time to meet the monthly pump test and quarterly valve test requirements of the Code Subsections IWP and IWV.
The inspector did not identify any discrepancies and had no further questions in this area.
3.
Containment Integrated Leak Rate Test a.
General On September 5-7, 1979, Maine Yankee Atomic Power Station performed a CILRT at a pressure of Pt (28 psig). The test was performed in accor-dance with test procedure 3.17.1, " Class A - Integrated Containment Leak Rate Test," Revision 1, dated May 16, 1979.
The inspector reviewed the procedure, witnessed various portions of the test, and independently verified the test calculations.
Details of the test are discussed below.
The inspector had no further questions or comments other than those which follow.
b.
10 CFR 50, Appendix J, states that fluid systems that are part of the reactor coolant pressure boundary and are open directlu to the contain-ment atmosphere under post-accident conditions and b nome an extension of the boundary of the containment shall be opened or vented to the containment atmosphere dur#ng the CILRT.
.iditionally, Appendix J states that all vented systems shall be drained of water or other fluids to the extent necessary to assure exposure of the system contain-ment isolation valves to containment air test pressure and to assure they will be subjected to the post-accident differential pressure.
During the CILRT conducted by Maine Yankee, liquid filled systems were neither drained, nor vented to the containment atmosphere as required.
This method of conducting a CILRT is unresolved pending further review by the NRC (309/79-13-01).
1506 347
.
.
c.
Instrumentation The inspector reviewed the calibration information for the test resis-tance temperature detectors, dew point instruments, pressure detectors, and the verification test flow meter to verify traceability to nation-ally recognized standards. All instrumentation was properly calibrated and suitably traceable.
d.
Chronology 9/5 1050 - Containment inspection completed.
1535 - Compressors started, commenced pressurizing containment.
9/6 0346 - Containment pressurization completed.
1530 - Containment leakage found through #3 steam generator.
SG isolated, test continued with SG pressurized.
1854 - Containaent repressurized to greater than 28 psig.
2000 - Commence CILRT.
9/7 2000 - Completed CILRT.
2100 - Commenced verification test by pump back method.
2230 - Verification test completed.
e.
CILRT Results On September 7,1979, the CILRT was completed. The inspector's calcu-lated results are summarized below.
(Results stated in weight percent per day unless otherwise stated.)
Acceptance Item Criteria Results (1)
CILRT Leak Rate by Mass
+ 0.025
--
Point Technique (2) CILRT Leak Rate by Mass 0.0521
+ 0.006 Point at the Upper 95%
Confidence Level I 506 348
.
.
(3)
Supplemental Verifica-0.25L 0.17L t
t tion Test Difference 4.
Unresolved Items Items about which more information is required to determine acceptability are considered unresolved.
Paragraph 3b. of this reports contains an unresolved item.
5.
Exit Interview At the inspection's end, the inspector held a meeting /see Detail 1 for
-
attendees) to discuss the inspection scope and findings.
The unresolved item was discussed.
1506 349
.