IR 05000336/1979020
| ML19256E241 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/14/1979 |
| From: | Caphton D, Rekito W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19256E240 | List: |
| References | |
| 50-336-79-20, NUDOCS 7911020012 | |
| Download: ML19256E241 (6) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION I
Report No.
50-336/79-20 Docket No.
50-336 License No.
DPR-65 Priority Category C
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Licensee:
Northeast Nuclear Energy Company P.O. Box 270 Hartford, Connecticut 06101 Facility Name:
Millstone Nuclear Power Station, Unit 2 Inspection At:
Waterford, Connecticut Inspection Conducted: July 24-27. 4979 ~
k @l 9[/2 [79 Inspectors:
W. A. Rekito, Reactor Inspector
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date
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Approved by:
c1 D. L. Cajihton, Chief, Nuclear Support
' dat'e Section No.1, RO&NS Branch Inspection Summary:
Inspection on July 24-27 1979 (Report No. 50-336/79-20)
Areas Inspected:
Routine, unannounced inspection by a regional based inspector of the inservice test program for pumps and valves, and licensee action on previous inspection findings.
The inspection involved 26 inspector-hours on site by one NRC regional based inspector.
Results:
Ne items of noncompliance or deviations were identified.
1256 073 Region I Form 167 (August 1979)
79110 20
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DETAILS 1.
Persons Contacted T. Blanchard, ISI Coordinator
- E. Farrell, Unit Superintendent
- J. Opeka, Site Superintendent
- S. Scace, Engineering Supervisor
- J. Stansbury, ISI Coordinator R. Stratman, Engineer NRC Personnel T. Shedlosky, Resident Inspector The inspector also interviewed other licensee personnel during the course of the inspection.
They included members of the engineering and operat-ing staffs.
2.
Previous Inspection Item Update (Closed) Inspector Followup Item (336/79-11-02):
The licensee issued LER 79-11/3L-0, describing their inability to confirm that the combined mea-sured leakage rate for Types B and C Local Leak Rate Testing was less than 0.60 La required by Technical Specification.3.6.1.2.b.
The inspector also reviewed approved revisions to the Typer 8 and C Local Leak Rate Testing procedures (SP 2605C, Rev. 3 and SP 2605D, Rev. 4) which include the requirement to measure and record a before-repair leakage prior to any repair or modification.
This corrective action will facilitate accurate reporting and does meet the intent of Section III of Appendix J to 10 CFR 50.
This item is closed.
3.
Inservice Testing of Pumps a.
Documents Reviewed
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ASME Boiler and Pressure Vessel Code,Section XI, Subsection IWP, " Inservice Testing of Pumps in Nuclear Power Plants" 1974 edition with Summer 1975 Addenda
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Procedure EN 21100, Rev. 0, Maintenance of Inservice Inspection Records Procedure ACP-QA-9.06, Rev. 1, Inservice Inspection Program
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Denotes those present at the exit interview.
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Procedure EN 21101, Rev. O, ISI Pump and Valve Operability
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Evaluation Procedure EN 21122, Rev. O, Spent Fuel Pool Cooling Pump 'B'
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(P-13B) Operational Readiness Test Procedure ACP-QA-2.028, Rev. 4, Retests
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Procedure EN 21102, Rev. O, Service Water Pump 'A' (P-5A)
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Operational Readiness Test Procedure EN 21115, Rev. O, LPSI Pump 'B' (P-42B) Operational
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Readiness Test
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Millstone Nuclear Power Station, Unit No. 2 Inservice Inspec-tion and Testing Program for Pumps, v'alves, and Pressure Tests for the 20 Month Period 4-26-79 to 12-26-80.
(Program Submit-tal to NRC)
Plant Design Change Request No. 2-112-79, for installation of
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permanent gages as required for IST.
b.
Scope The inspector verified that all applicable pumps, as identified in the program submittal, were tested by approved procedures.
On a sampling basis the inspector also reviewed the licensee's implemen-tation program for conformance with Subsection IWP of Section XI of ASME B&PV Code and with his submittals to the NRC.
This included review of implementing test procedures, administrative control pro-cedures, test records, and test results evaluation records.
With the exceptions noted below the inspector found no discrepancies and had no further questions in this area.
c.
The inspector identified that the Service Water Pump Operational Readiness Test Procedure EN 21102 incorrectly required a minimum lubricating water pressure to be greater than the normal operating value.
The licensee immediately issued a change to the procedure to correct this error.
Based upon the corrective action taken, this item is resolved and acceptable.
d.
The Spent Fuel Cooling Pump Operational Readiness Test Procedure EN 21102 required the measured flowrate to be varied to equal the reference value of 850 gpm, in order to meet the intent of the code paragraph IWP-3100.
Review of test records and discussions with the test coordinator revealed the operating difficulty to duplicate this value exactly as required by the procedure.
The licensee corrected this discrepancy by issuing a change to the pro-cedure which assigned an acceptable r uge of measured flowrate.
This item is resolved and acceptable.
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The Operability Evaluation Procedure EN 21101 did not specify or e.
reference the corrective action required by IWP 3230(a) when test values fall within the " Alert Range" of acceptance criteria.
This item is unresolved pending revision of the procedure to conform with requirements of IWP 3230(a).
The item is designated (336/79-20-01).
f.
The Operability Evaluation Procedure EN 21101 did not provide needed guidance for corrective action when test values fall within the
" Required Action Range" of acceptance criteria.
In this area the inspector noted relief requests from the requirements of IWP-3230(c),
IWV-3410(c)(3), IWV-3410(g) and IWV-3520(c) identified in the licensee's Program Submittal to NRR.
These sections of the code not only require specific actions be taken but also require that a com-ponent be declared inoperative within a specified time if the condi-tions are not corrected.
The commitment to provide alternate specific defined corrective action in this implementation procedure is part of the basis for the relief requests referenced above.
This item applies to inservice testing of pumps and valves and is unresolved.
The item is designated (336/79-20-02).
g.
Duration of Tests The pump operational readiness test procedures reviewed did not address the requirements of IWP-3500 to run a pump for at least five minutes under stable conditions, then measure and record the required data.
This item is unresolved pending revision of procedures to conform with requirements of IWP-3500.
The item is designated (336/79-20-03).
4.
Inservice Testing of Valves Documents Reviewed (in addition to those identified in paragraph 3.a.)
a.
ASME Boiler and Pressure Vessel Code,Section XI, Subsection IWV,
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" Inservice Testing of Valves in Nuclear Power Plants", 1974 edi-tion with Summer 1975 Addenda.
Procedure EN 21131, Rev. 0, Chemical and Volume Control System
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Valves Operational Readiness Tests Procedure EN 21133, Rev. O, Reactor Coolant System Valves Ope-
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rational Readiness Tests Procedure EN 21129, ilev. 0, Containment Isolation Valves Ope-
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rational Readiness Tests Procedure EN 21128, Rev. 0, Chilled Water System Valves Ope-
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rational Readiness Tests 1256 076
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b.
Scope The inspector verified, on a sampling basis, that all applicable valves identified in the program submittal were tested by approved procedures. The inspector also reviewed the licensee's implementa-tion program for conformance with Subsection IWV of Section XI of ASME B&PV Code and with his submittals to the NRC.
This included review of implementing test procedures, administrative control proce-dures, test records, and test results evaluation records.
With the exceptions noted below the inspector found no discrepancies and had no further questions in this area.
c.
Check Valve Tests Some check valves, such as pump discharge checks, perform a dual function and are sometimes open and sometimes closed.
These valves, in accordance with IWV-3520, should be tested in both the open direction and the closed direction to demonstrate that they are able to fulfill their design function.
The Charging Pumps and Chilled Water Pump Discharge check valves are examples of dual function valves which are not tested in both directions.
This' item is unresolved pending revision of the procedures to conform with requirements of IWV 3520.
The item is designated (336/79-20-04).
d.
Valve Stroke Times The test of valve 2-FW-43A exceeded the " maximum stroke time allowed."
After performina maintenance, a retest resulted in just meeting the maximum stroke time limit of 20 seconds.
Further corrective action, documented on a memo to file dated 7-16-79, was to change the maxi-mum stroke time limit to 30 seconds.
The original value (20 seconds)
is specified in the program submittal.
Official approval of the program submittal is pending final review by NRR.
The licensee stated he would notify NRR of this test pro-gram change via a program submittal change request.
This item is unresolved pending NRR notification and further NRC review of this
. change.
The item is designated (336/79-20-05).
5.
Inservice Test Witness a.
Scope The inspector witnessed the Operational Readiness Tests of the Spent Fuel Cooling Pump "B" and the Low Pressure Safety Injection Pump "B".
The inspector verified that the tests were being conducted in accor-dance with approved procedures.
The tests measured the pumps' suc-tion pressure, discharge pressure, flowrate (SFC Pump only), and bearing vibration.
The test results appeared to be acceptable.
With the one exception noted below the inspector found no discrepan-cies and had no further questions in this area.
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b.
Instrument Calibration IWP 4113 requires that all instruments used for tests shall be veri-fied for calibration validity on a regular basis.
While witnessing the test of the "B" Spent Fuel Cooling Pump the inspector observed that the discharge pressure gage had exceeded its calibration due ac. e and the suction pressure gage had no calibration sticker.
After questioning, the licensee's representative explained that the suc-tion pressure gages on most pumps being tested were temporary instal-lations.
The permanent gages are on order and are part of an approved Plant Design Change Request #2-112-79, converting previous " Test Connections" to " Pressure Indicators" in support of the IST program.
He also explained that all other instruments used in the IST program are on the routine Plant Maintenance Calibration Schedule except for the "B" Spent Fuel Cooling Pump discharge pressure gage which was inadvertantly left off.
As an interim measure, until the permanent gages are installed, several calibrated temporary gages have been obtained and will be used for test purposes.
This item is considered to be resolved but will receive further review in a subsequent inspection.
The item is designated (336/79-20-06).
6.
Plant Tour The inspector conducted a plant tour and observed the licensee's control of Section XI, Subsection IWV, Category E locked valves.
The systems observed included High Pressure Safety Injection, Low Pressure Safety Injection, and Containment Spray.
No discrepancies were identified and the inspector had no further questions in this area.
7.
Unresolved Items Items about which more information is required to determine acceptability are considered unresolved.
Paragraphs 3, 4, and 5 of this report contain unresolved items.
8.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1)
at the conclusion of the inspection on July 27, 1979.
The inspector summarized the scope and findings of the inspection at that time.
1256 07B