IR 05000333/1979003
| ML19241A919 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 05/03/1979 |
| From: | Caphton D, Higgins J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19241A911 | List: |
| References | |
| 50-333-79-03, 50-333-79-3, NUDOCS 7907110426 | |
| Download: ML19241A919 (10) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-333/79-03 Docket No. 50-333 License No. DPR-59 Priority
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Category C
Licensee: Power Authority of the State of New York P. O. Box 41 Lycuming, New York 13093 Facility Name: James A. FitzPatrick Nuclear Power Plant Inspection at: Scriba, New York Inspection conduct.ed:
March 20-23, 1979 I l Inspectors:
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6'/3/79 J. C. HIggins, Rea$ tor Inspector date signed date signed data si ned Approved by:
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D. L. Caphton, Chief, Nuclear $ppport Ma ts' sig ned Section No. 1, RO&NS Branch Insoection Summary:
Inspection on March 20-23,1979 (Recort No. 50-333/79-03):
Areas Inspected:
Routine unannounced inspecticn by a regional based inspector of backshif t operations, containment leak rate testing, inservice testing of pumps and valves and previous inspection findings.
The inspection involved 24.5 inspector-hcurs on site by one NRC regional based inspector.
Results:
No items of noncompliance were identified.
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Recion I Form 12 (RUv. Acril 77)
DETAILS 1.
Persons Contacted The below listed technical and supervisory personnel were contacted.
- E. Abbott, Operating Superintendent R. Baker, Maintenance Superintendent V. Childs, Assistant to Resident Manager R. Converse, Assistant Operating Superintendent W. Fernandez, Assistant to Maintenance Superintendent J. Ford, I&C Superintendent
- J. Hoddy, Reliability and Performance Supervisor S. Hudson, Shift Supervisor H. Keith, Assistant to I&C Superintendent
- J.
Leonard, Resident Manager
- R. Pasternak, Superintendent of Power W. Sanborn, Shift Supervisor
- denot,; those present at the exit interview.
The inspector also talked with and interviewed several other members of the technical and operating staffs.
2.
Licensee Action on Previous Inspection Findinos (Closed) Item of Noncompliance (333/77-22-09):
This item was also reviewed in report 77-32.
The inspector reviewed records of the last several snubber visual inspect ons and several i
other com 'eted surveillance tests and noted that there was no difficu,ty in retrieving them.
The Record Management System is still being backfitted with past records, but the inspector noted no problems with present retrievability.
This item is closed.
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(Closed) Unresolved item (333/78-22-01):
This item was also reviewed in report 78-26.
All penetrations isolated during the CILRT received local leak rate tests befo'e and after repair.
The post-repair leakage has been adde:d to the Type A test leakage.
Results are summari;:ed in TaNe 1.
The licensee has included in Part C of his Leak Rate Test Report the test results corrected for instrument error.
The leakage rate was acceptable with the corrections applied.
This item is closed.
(Closed) Unresolved Item (333/78-22-02):
While reviewing this unresolved item, the licensee verified that Technical Specification (TS) Surveillance Tests were not performed on newly installed containmer,t isolation valves and submitted Licensee Event Report 78-112 dai.ed January 25, 1979.
Procedures have since been revised and the valves tested satisfactorily.
Additionally, the inspector reviewed a draft TS change which will incorporate these valves into Table 3.7.1 of the TS's.
This item is closed.
(Closed) Unresolved Item (333/78-22-05):
The inspector reviewed Maintenance Procedure tb. 100.2, Raision 1, dated December 5, 1978, for snubber visual inspections and noted that the acceptance criteria, step 7.2, now specify that a snubber is inoperable if the piston setting is unsatisfactory.
This item is closed.
(Closed) Followup Item (333/78-22-06):
The iaspector reviewed the licensee's procedures for inservice testing of pumps and valves under Section XI.
Results of this review are discussed in paragraph 5 of this report.
(Closed) Unresolved Itea (333/78-22-07):
e inspector reviewed the latest revision to SP-2 dated December 1, 1978, and noted that it contained precautions against initiating the Main Steam Leak Collection System if the Main Condenser is intact and that it specified actuation of the system within approximately 20 minutes of an accident requiring its use.
This item is closed.
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(Closed) Unresolved Item (333/78-22-08):
The inspector
reviewed Revision 6 to OP-1 dated February 27, 1979, and j
noted that it was a complete rewrite of Revision 5.
The new l
revisien, however, contains appropriate references to the Main St.am Leak Collection System.
This item is closed.
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(Closed) Unresolved Item (333/78-26-01):
The inspectcr
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reviewed information from the Dewcel calibration facility a
which documented their calibration traceable to the National j
Bureau of Standards.
This item is closed.
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(0 pen) Unresolved Items (333/77-32-04 and 07):
The licensee's j
current Type B&C leakage total is less than 0.60 La utilizing j
the conservative ratio for MSIV leakage and the smaller value
(3216 SCFD) of leakage for an acceptance c d teria.
The
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licensee procedures have not been revised to equire these i
two conservatisms.
The licensee's representative stated that f
these conservatisms may not be required.
The inspector noted that, although the licensee had produced no valid basis for
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his position, current leakage is within the conservative
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limits.
This item emains unresolved.
(0 pen) Unresolved Item (333/78-26-02):
As discussed in this item and as confirred by onsite review of final leakage rate data, the initial attempt of tne periodic Type A test failed to meet the acceptance criteria of 0.75 La or 0.375 %/ Day.
The insoector determined this initial leak rato by taking the final leak rate at the 95% upper confidence level and adding corrections for flooded lines and lines isolated during the i
Type A test.
The initial leak rate at the 95% upper confi-
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dence level was thus deterrined to be 0.419 %/ Day plus some small unknown value of leakage through the nine valve packings a
which were tightened during the test.
This item remains open p
j pending the review of the licensee's future test schedule by the Commission, as required by paragraph III.A.6.(a) of Appendix J to 10 CFR 50.
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3.
Backshift Inspection The inspector commenced the inspection at 6:45 p.m., on March 20, 1979.
The following items were reviewed by the inspector during this phase of the inspection:
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Alertness of security personnel and integrity of portions of the protected area boundary;
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Cont.al room manning;
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Plant in cold shutdown as required by NRC Order;
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Con +.rol room logs and various plant parameters on the control panels;
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Core instrumentation;
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Reasons for selected lighted annunciators;
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Status of maintenance in progress; and
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General condition of facility, including Reactor Building, Turbine Building, Cable Spreading Areas and Relay Room.
No unacceptable conditions were identified.
4.
Containment Leak Rate Testina a.
General The inspector reviewed the licensee's leak rate test rc? ort titled " Reactor Containment Building Integrated Leak Rate Test, Type A, B and C Periodic Tests for January, 1976 to November, 1978" and related procedures and data onsite.
The documents were reviewed for accurate data transcription, proper instrument calibration, correctness of analytical methods, and proper additions and corrections to the final leak rate.
No items of noncompliance were identified.
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b.
Satisfactory Containment Integrated Leak Rate Test (CILRT)
The inspector performed calculations and using raw data independently verified:
the inclusion of instrument calibration corrections, the computed contained air mass values, the containment leakage rate, the 95% upper confidence level on the leakage rate, and local leak rate test additions.
Test results are summarized in Table 1.
The inspector's independent calculations agree substantially with the licensee's values and indicate that the CILRT was satisfactorily completed.
c.
Main Steam Isolation Valves (MSIV's)
During tne CILRT excessive leakage was detected through the A main steam line and an " air plug" was established tween the two MSIV's.
Thus valve repairs and local
- ak rate testing after the CILRT were required on these valves and the results were added to the CILRT leakage.
While the summation of all leakages met the Type A test acceptance criteria (see Table 1), the outboard A-MSIV was unable to meet its individual acceptance criteria of 276 standard cubic feet per day (SCFD).
Leakage was 295 SCFD.
The plant's licensee (Table 3.7.2 of TS) was amended to allow operation during cycle 3 with the A outboard MSIV leakage not to exceed 300 SCFD, provided the total leakage of the 4 outboard MSIV's did not exceed 1104 SCFD.
During the current inspection the plant was shutdown and the licensee retested the A-outboard MSIV.
The leakage rate was 407.71 SCFD, thus requiring valve repairs and further testing prior to plant startup.
The inspector had no further questions in this area at this time.
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5.
Inservice Testing of Pumps a.
Documents Reviewed
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Initial Inservice Testing Program for Pumps and Valves, submitted to the NRC on September 1, 1978.
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"RHR Pump Flow Rate Test (ISI)," F-ST-2A, Revision 3, January 12, 1979.
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"RHR Pump Operability Test (ISI)," F-ST-28, Revision 1, January 12, 1979.
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"RHR Service Water Pump Flow Rate Test," F-ST-2E, Revision 3, January 15, 1979.
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"RHR Service Water Pump and MOV Operability Test,"
F-ST-2R, Revision 3, January 12, 1979.
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" Core Spray Pump Flow Rate Test (ISI)," F-ST-3A, Revision 1, January 15, 1979.
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"HPCI Flow Rate Test (ISI)," F-ST-48, Revision 5, February 17, 1979.
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" Standby Liquid Control Pump Functional Test (ISI),"
F-ST-6A, Revision 5, January 3, 1979.
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Subsection IWP of Section XI to the ASME Boiler and Pressure Vessel Code, 1974 Edition through Summer 1975 Addenda (IWP).
b.
Scoce The inspector reviewed the licensee's pump test procedures for conformance with Subsection 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 results for pump tests performed since program implementation November 28, 1978.
The inspector noted that a meeting was scheduled in April between the licensee and the NRC to discuss requested exemptions from Section XI and with the exception of the below items had no further questions in the pump testing area.
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c.
Reference Conditions In orde" that test conditior.s may be readily duplicated during s11 inservice testing,Section XI requires that referenc ccnditions of flow or differential pressure and pump, speed be established.
Several of the pump test procedures reviewed did not establish these reference to.Mitions for the test in question (e.g., RHR, RHR Service Water and HPCI).
This item is unresolved (333/79-03-01).
d.
Test Analysis None of the pump test procedures reviewed contained reference values for measured parameters, the acceptance criteria specified in IWP-3210, the requirement for a 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> review of results, or the specified corrective actions of IWP-3230.
This item is unresolved (333/79-03-02).
e.
Pumo Lubricant The pump test procedures reviewed did not verify proper pump lubricant level or pressure as required by IWP-3100.
This item is unresolved (333/79-03-03).
f.
Minimum Run Time The pump test procedures reviewed did not specify the minimum run time of 5 minutes prior to data taking required by IWP-3500.
The item is unresolved (333/79-03-04).
6.
Inservice Testing of Valves a.
Scope The inspector reviewed the licensee's valve testing procedures for conformance with Subsection 'W of Section XI to the ASME Boiler and Pressure Vessel ade (IWV) as modified by his submittals to the NRC.
The inspector reviewed a sampling of completed valve tests performed since program implementation on November 28, 1978.
With the exception of the below items the inspector had no further questions in this area at this time.
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b.
Valve Stroke Tiaes Many of the liceasee's procedures do not specify muimum stroke times for Category B valves as required by IW-3410(c).
Addit.ionally, t.he procecures do not compare valve stroke times with those of previous tests to determine degradation.
This item is unresolved (333/79-03-05).
7.
Unresolved Items Items abou', which more information is required to determine acceptability are considered unresolved.
Paragraphs 5 and 6 of this report contain unresolved items.
8.
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 items were identified.
The licensee's representative stated that every effort would be made to revise procedures to correct the unresolved items by May 1,
1979; and that if not revised by then, they would be completed before July 1,1979.
The inspector acknowledged these comments.
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IABLE 1 CILRT Conducted at P (45 PSIG) at J. A. FitzPatrick Item Acceptance Criteria Reported Results Inspector's Findings 1. Containment Leak Rate
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0.292 %/ Day 0.292 %/ Day (Mass Point)
2. Upper 95% Confidence
< 0.375 %/ Day 0.298 %/ Day 0.298 %/ Day Level on Leak Rate (Mass Point)
3. Local Leak Rate Test
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0.038 %/ Day 0.045 %/ Day Additions (Type B&C)
4. Coiltainment Leak Rate
< 0.375 %/ Day 0.336 %/ Day 0.343 %/ Day at Upper 95% Confi-dence Level Plus Required Additions 5. Supplemental Verifi-
< 99 lbm 32.1 lbm 32.7 lbm cation Test Difference
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