IR 05000029/1979002
| ML19270G604 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 03/07/1979 |
| From: | Caphton D, Higgins J, Tanya Smith NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19270G593 | List: |
| References | |
| 50-029-79-02, 50-29-79-2, NUDOCS 7906140164 | |
| Download: ML19270G604 (9) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-029/79-02 Docket No.50-029 License No.
DPR-3 Priority
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Category C
Licensee:
Yankee Atomic Electric Company 20 Turnpike Road Westborough, Massachusetts 01581 Facility Name:
Yankee Nuclear Power Station (Yankee Rowe)
Inspection at:
Rowe, Massachusetts Inspection cond eted:
Feb uary,13-16,1979 G/
M 67N Inspectors:
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C its'
Inspector
/ da'te ' signed J.TN.HiaM) Reacfor,fn/
wh/77 T # li. ' Smith', Reactor II)spector
/dath signed f bo b 3/7/79
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/Repctor Inspector da'te signed Approved by:
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3/78 0. L. Caph'tod, Chief, Nuclear Support
/date jigned Section No. 1, R0&NS Branch Inspection Summary:
Inspection on February 13-16,1979 (Report No. 50-029/79-02)
Areas Inspected: Routine, unannounced inspection by regional based inspectors of licensee action on previous inspection findings and the inservice test programs for pumps and valves. The inspection involved 63 inspector-hours on site by three NRC regional based inspectors.
Results: Of the two areas inspected, no items of noncompliance were found in one area; one item of noncompliance was found in the other area (infraction - failure to exercise specified valves within the required time period - paragraph 4.c).
2270 135 79061401bi Region I Form 12 (Rev. April 77)
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DETAILS 1.
Persons Contacted The following technical and supervisory level personnel were contacted:
- H. Autio, Station Superintendent R. Durfey, Technical Assistant
- M. Ebert, Plant Reactor Engineer
- L. French, Engineering Assistant
- T. Henderson, Technical Assistant P. Laird, Maintenance Supervisor J. Lance, ISI Coordinator D. Long, Graduate Engineer
- R. Randall, Engineering Assistant
- J. Staub, Technical Assistant to Plant Superintendent denotes those present at the exit interview
The inspector also talked with and interviewed several other licensee employees, including members of the technical, engineering and operations staffs.
2.
Licensee Action on Previous Inspection Findings (0 pen) Unresolved Item (029/77-26-01):
The inspector reviewed the cur-rent revision of the licensee's procedure for conducting Type B and C tests, OP-4702, Revision 6, titled " Vapor Container Type B and C Pene-tration Tests." The status of each part of the unresolved item is dis-cussed below as originally numbered.
(1) The current procedure does not require that valves which are to be Type C tested be closed by their normal means.
(open)
(2) The containment mass value used in pressure decay calculations has been corrected.
(closed)
(3) The procedure to test electrical penetrations has been modified and is satisfactory.
(closed)
(4) The cavity purification blank flange has been added to the pro-cedure for Type B testing.
(closed)
2270 136 590614 h
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(5) The frequency statement for Type C tests has not been corrected to conform to the requirements of 10 CFR 50 Appendix J.
(open)
(6) The frequency statement in the current procedure for airlock tests does not reflect the requirements of 10 CFR 50 Appendix J.
(open)
Subparts (2), (3) and (4) are considered resolved.
The item remains open pending resolution of (1), (5) and (6).
(Closed) Unresolved Item (029/77-26-02):
The inspector reviewed the administrative control system in effect for test, vent and drain lines which tap into piping systems inside containment isolation valves.
The controls are considered adequate and this item is resolved.
(Closed) Unresolved Item (029/77-26-03):
The testing requirements for electrical penetrations have been incorporated into the Type B and C test procedure, OP-4702, Revision 6.
The procedure adequately covers the testing requirements of electrical penetrations.
This item is resolved.
(0 pen) Unresolved Item (029/77-11-03):
The inspector reviewed the cur-rent revision of the licensee's procedure for conducting the Type A test, OP-4701, Revision 4, " Vapor Container Type A Leakage Test." The status of each part of the unresolved item is discussed below as origi-nally numbered.
Items (2) to (5) and (7) to (16) have been corrected or addressed in the revised procedure.
These items are considered resolved.
(1) The current procedure does not require that the primary system be vented during the Type A test as required by 10 CFR Appendix J.
(open)
(6) The current procedure revision does not contain precaution and limitation statements relative to repairing identified containment leak paths during the Type A test.
(open)
2270 137
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(Closed) Unresolved Item (029/77-11-05):
The inspector reviewed the data supplied by the manufacturer of the pressure instruments used in the Type A test. The manufacturer stated that a negligible error (0.0015%) is introduced by calibrating the instrument with the sensor in a vertical position and using it during the Type A test with the sensor in the horizontal position.
The information supplied also clarified the procedure to temperature compensate the pressure in-strument.
This item is resolved.
(Closed) Unresolved Item (029/77-11-06):
The inspector reviewed RTD calibration documentation which demonstrated calibration traceability to nationally recognized standards.
Based upon this review the inspector had no further questions and the matter is considered resolved.
3.
Inservice Testing of Pumps a.
Documents Reviewed
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Letter from R. Groce (YAEC) to NRC dated December 19, 1977,
" Inservice Inspection Update"
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Letter from D. Moody (YAEC) to NRC dated February 16, 1978,
" Requests for Relief from ASME Section XI Code Requirements" Letter from D. Ziemam (NRC) to R. Groce (YAEC) dated March 13,
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1978 OP-4208, Revision 6, " Flow Test of Two LPSI Pumps on Normal
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AC Power" OP-4204, Revision 13, " Monthly Test of Special Operation of
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the Safety Injection Pumps" OP-4211, Revision 6, " Emergency Boiler Feedwater System Opera-
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bility Test" 2270 138
b.
Scope The inspector reviewed the licensee's pump test procedures for conformance with Subsection IWP of Section XI (IWP) as modified by his submittals to the NRC.
The inspector verified that testing of all pumps in the program submittal was covered by properly approved procedures and that the procedures met the requirements of IWP. The inspector reviewed a sampling of completed test re-sults for pump tests performed between March 1978 and January 1979.
With the exception of the below items, the inspector had no further questions in the pump testing area.
c.
Reference Values Reference values for the pumps in the program as described in Section XI, paragraph IWP-3110 (IWP-3110) have not been established for differential pressure or pump speed.
This item is unresolved (0.29/79-02-02).
d.
Acceptance Criteria The acceptance criteria of Table IWP-3100-2 and the required corrective actions of IWP-3230 have not been incorporated into the licensee's procedure.
This item is unresolved (029/79-02-03).
e.
Differential Pressures The pump differential pressures are not determined by the licensee's procedures as required by IWP-3100.
The procedures measure tank level at the pump suction and pump discharge pressure.
This item is unresolved (029/79-02-04).
f.
Vibration and Bearing Temperatures The licensee's pump test procedures currently do not contain any requirement for taking vibration data and pump bearing temperatures.
The data, however, is being taken on unofficial data sheets.
This item is unresolved pending revision of the procedures to re-quire measurement of the data specified in IWP-3100 (029/79-02-05).
2270 139
g.
Time Allowed for Analysis of Tests The procedures do not specify the 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> analysis requirement of IWP-3220.
This item is unresolved (029/79-02-06).
h.
Instrument Range IWP-4111 requires that the full scale range of each instrument not exceed four times the reference value.
The Alnor tempera-ture probe being used for bearing temperature measurement does not meet this requirement.
This item is unresolved (029/79-02-07).
4.
Inservice Testing of Valves a.
Documents Reviewed In addition to the documents listed in 3.a, the inspector also reviewed the following procedures:
OP-4705, Revision 1, " Quarterly Inservice Valve Operability
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Check"
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OP-4217, Revision 5, " Charging System Operability Test" OP-4214, Revision 6, " Chemical Shutdown System Operability
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Check" OP-4517, Revision 2, " Surveillance of Motor Operated Valves"
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OP-4518, Revision 1, " Travel Time of Motor Operated Valves -
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Master List" Job Order 78-165, Tests of the 12 Main Steam Safety Valves
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Job Order 78-168, Tests of the 12 Pressurizer Code Safety
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Valves by Wyle Laboratory 2270 140
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b.
Scope The inspector reviewed the licensee's valve testing procedures for conformance with Subsection IWV of Section XI (IWV) as modified by his submittals to the NRC.
On a sampling basis the inspector verfied that all valves listed in the licensee's program submittal were tested by properly approved procedures.
The inspector also ;eviewed a sampling of completed valve test results performed between March 1978 and January 1979.
With the exception of the below items, the inspector had no further questions in this area.
c.
Quarterly Valve Exercising 10 CFR 50.55a(g)(4) requires that water cooled power reactors meet Section XI of the ASME Boiler and Pressure Vessel Code and paragraph IWV-3410(a) of Section XI which requires that Category A and B valves be exercised at least once every 3 months.
Contrary to the above, the Category B valves listed in OP-4705, Revision 1, (e.g. CH-MOV-521, DW-M0V-655, HV-V-7 and DW-V-777)
were not exercised from August 8,1978 to February 16, 1979.
This is an item of noncompliance at the infraction level (029/79-02-01).
The licensee's representative later informed the inspector via telephone that all valves in OP-4705 were satisfactorily exer-cised on February 16, 1979.
d.
Stroke Time Comparisons OP-4705 for quarterly valve exercising does not contain the re-quirement of IWV-3410(c)(3) for comparison of stroke times with those from the previous test (or an average of previous tests).
This item is unresolved (029/79-02-08).
e.
Fail-Safe Actuators The licensee's valve testing procedures do not appear to address the testing requirements of IWV 3410(e) for valves with fail-safe actuators.
This item is unresolved pending review of these valves by the licensee and incorporation of the required testing into his procedures (029/79-02-09).
2270 141 P
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f.
Summary Listing The summary listing of all valve testing being maintained per IWV-6210 does not include all valves in the program (e.g. DW-V-757 is not included).
This item is unresolved pending a review by the licensee to en-sure that all required valves are included in the sumary listing (029/79-02-10).
g.
Valve Motor Current Readings IWV-3300 requires a check of each refueling outage of valve position indication for valves which are inaccessible during operation. The licensee performs this verification of valve position indication by taking current readings on the valve motor operators in OP-4517. Tite inspector noted that the procedure did not contain any acceptance criteria or required evaluation of the current readings.
This item is unresolved (029/79-02-11).
5.
Pump Test Witnessing During the course of the inspection the inspectors observed the in-service tests performed on the emergency boiler feed pump, number 2 low pressure safety injection pump and number 2 high pressure safety injection pump. These tests were performed by qualified operators using approved procedures.
The results appeared satisfactory-The inspector reviewed a sampling of instrumentation used for these tests to verify that requirements of Article IWP-4000 were met and that calibrations were traceable to the National Bureau of Standards.
With the exception of the temperature instrument identified in para-graph 3.h, the inspector had no further questions in this area.
During inspection of pump testing, the inspector observed three small pipe hangers in instrument lines to the pump discharge lines that were not properly attached.
Maintenance personnel were promptly dispatched and repaired the hangers.
2270 142
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6.
Inservice Inspection and Testing Meeting During the course of the inspection the inspectors participated in various sessions of a meeting held between the licensee and the NRC's Office of Nuclear Reactor Regulation concerning the licensee's Inservice Inspection and Test Program under Section XI of the ASME Boiler and Pressure Vessel Code.
The various components to be in-cluded in the programs and the licensee's requested reliefs from the Code were discussed in detail.
Based on the results of the meeting, the licensee's representatives agreed to revise and resubmit the pro-gram and their requests for relief.
7.
Unresolved Items Items about which more information is required to determine accepta-bility are considered unresolved.
Paragraphs 3 and 4 of this report contain unresolved items.
8.
Exit Interview _
At the inspection's end, the inspectors held a meeting (see Detail 1 for attendees) to discuss the inspection scope and findings. The Item of Noncompliance and unresolved items were identified.
2270 143
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