IR 05000245/1980019
| ML19341B327 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 11/04/1980 |
| From: | Caphton D, Petrone C, Rekito W, Wiggins J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19341B325 | List: |
| References | |
| 50-245-80-19, NUDOCS 8101300727 | |
| Download: ML19341B327 (7) | |
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O-U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
50-245/80-19 Docket No.
50-245 License No. DPR-21 Priority Category C
--s Licensee:
Northeast Nuclear Energy Company P. O. Box 270 Hartford, Connecticut 06101 Facili';j Name:
Millstone Nuclear Power Station, Unit 1 Inspection at:
Waterford, Connecticut Inspection conducted:
October 6-9, 1980 Inspectors:
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//- 4'-F0 W. Rekito, Reactor inspector date signed 44. W
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J. Wiggins, Reactor 4nspector date signed W fpU'
ll-W - 5?o C Petgne Reac # Inspector da e signed Approved by:
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D. L. CapnTdh. CMef, Nuclear Support
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Section No.1, RO&NS Branch Inspection Summary:
Inspection on October 6-9, 1980 (Report No. 50-245/80-19)
Areas Inspected: Routine, unannounced inspection of the containment integrated l
leak rate test procedure; containment local leak rate testing; surveillance of j
pipe support and restraint systems; and licensee action on previous inspection findings.
The inspection involved 50 inspector-hours onsite by three region-based NRC inspectors.
l Results: No items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted NNECO P. Benyeda, Supervisory Control Operator L. Georgian, Engineer
- R.
Herbert, Unit 1 Superintendent
- E. Mroczka, Station Superintendent J. Nowell, Shift Supervisor R. Palmieri, Engineering Supervisor
- K. Thomas, Engineer Gineral Physics Corp.
E. Levinson, Supervisor Systems Projects NRC
- T. Shediosky R. Zimmerman
- denotes those present at the exit interview 2.
Licensee Action on Previous Inspection Findings:
(Closed) Unresolved Item (245/77-05-01):
Submission of Future CILRT Schedule.
NRR conducted a review of the future CILRT.chedule subsequent to t'e November 1976 Type A test failure.
A memorandum from K. R. Goller, NRR, to K. V. Seyfrit, IE, dated February 9,1978 stated that based on the licensee's prcposed corrective measures with regard to the test failure, a revised schedule for the CILRT was not necessary.
This item is resolved.
(Closed) Unresolved Item (245/77-05-02):
Draining systems during the
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CILRT.
In letters to the NRC dated July 29, 1977 and September 20, 1978 l
the licensee identified all systems not vented and drained for the Type A test along with the justifications for each.
This item is resolved.
(Closed) Unresolved Item (245/77-05-03):
CILRT Procedure.
The licensee is l
preparing a procedure to perform the 1980 CILRT.
Further discussion of this procedure is found in detail 3 of this report.
The concerns discussed in item 77-05-03 were addressed during the inspector review of the 1980
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This item is resolved.
(Closed) Unresolved Item (245/77-05-04):
Additional Type C Testing. The licensee has included plans for testing the valves in question in the
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September 20, 1978 Appendix J testing program description.
This document identifies that the Control Rod Drive (CRD) Return line has been rerouted to the feedwater line outside the feedwater containment isolation valves thus removing the local testing requirement for the CRD Return line. This item is resolved.
(0 pen) Unresolved Item (245/77-05-06):
Artificial Leakage Barriers. The inspector reviewed procedure SP623.14 Revision 2, dated April 14, 1919. The inspector was still able to identify possible artificial leakage barriers.
This area is further discussed in detail 4 of this report and the item remains open.
(Closed) Unresolved Item (245/77-05-12):
Reverse direction testing. The inspector reviewed the Appendix J testing program description submitted to NRR on September 20, 1978 which contained a list of primary containment valves and penetrations to be tested.
Valves which will be tested with the applied pressure in a direction opposite to their design safety function are identified in this document. Various system modifications are necessary to meet NRC criteria for reversed direction testing.
These modifications are discussed in detail 4 of this report.
As such, this item is closed and this matter will be tracked as part of item 80-19-05.
(Closed) Unresolved Item (245/77-05-10):
Test Vent and Drain Lines. The inspector noted that affixed to the test connections used for local leak rate testing are blue metal tags reading "LLRT Test Connection:
Normally Closed." At the end of each local leak rate test, the person performing the system restoration signs a test vent and drain connection verification sheet indicating that the test valve is shut and the cap is reinstalled.
This item is resolved.
(Closed) Open Item (245/78-25-01) (formerly Infraction 245/78-25-01):
Failure to test airlock.
The inspector reviewed test records for the airlock tests conducted December 19, 1979 and June 19, 1980.
These tests were conducted at 43 psig.
This item is closed.
(Closed) Unresolved Item (245/77-32-03):
This item, verification of snubber setpoints, has been superseded by unresolved item 79-15-03.
This item is closed and all concerns will be resolved under item 79-15-03.
(Closed) Unresolved Item (245/78-17-05):
The licersee has corrected Pipe Support Drawing A-4498 to reflect the as-built condition.
This item is closed.
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(0 pen) Unresolved Item (79-15-03):
No acceptance criteria for snubber piston extension.
The licensee has taken steps to establish these criteria.
Measurements have been taken on the installed Bergen-Patterson snubbers.
This data is being analyzed and will be used to determine acceptable snubber piston extension settings.
Procedure MP 739.1 already contains acceptance criteria for Grinnell snubber piston settings.
This item remains open pending further action by the licensee.
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(Closed) Deficiency (79-15-04):
Failure to follow procedure MP 739.1, Step 5.1.
Step 5.1 required that the hydraulic fluid level be recorded prior to snubber removal.
The licensee stated that this step was unnecessary since the snubbers were being removed for functional testing.
The inspector verified that the licensee had instructed persons involved on the necessity to properly follow procedures.
This item is closed.
3.
Containment Integrated Leak Rate Test (CILRT)
References:
10 CFR 50 Appendix J ANSI N 45.4 - 1972 ANS N 274 a.
Procedure
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The inspector reviewed the draft procedure for the 1980 Integrated Leak Rate Test for technical adequacy and for conformance to the requirements stated in the references listed above.
The inspector also discussed various aspects of the CILRT with the licensee's represen-tatives including current NRC positions concerning leak rate testing and the licensee's plans for the 1980 CILRT.
The following is a summary of inspection findings in this area:
(1) The procedure measures containment leak rate using the absolute method and total time calculations.
The inspector stated to representatives of the licensee that the NRC recognizes the absolute method with mass point calculations for determination of the acceptability of test results.
(2) The procedure does not specify the use of raw data corrected for instrument error in the leak rate calculation. Appendix J to 10 CFR 50 requires that test !eakage rates shall be calculated using absolute values corrected for instrument error.
(3) Appendix A to the draft procedure gives a method for correcting containment free volume for changes in reactor vessel, torus and drywell sump levels.
The procedure uses this corrected volume in the determination of instrument volume weighting fractions.
The inspector stated it is also necessary to use a corrected free volume in the actual leak rate calculation. The procedure does not address this point.
(4) The procedure should direct that the measured leak rate be corrected by addition of local leak rate test results for those systems that are not in the post accident condition during the Type A test.
(5) The inspector clarified the NRC position by stating the Type A test will be considered acceptable if the measured leak rate
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(Lam) at the 95% Upper Confidence Level, corrected for free volume changes and corrected for systems not in the post accident condition, is less than 0.75 La.
(6) The inspector noted that the procedure incorrectly stipulates a minimum test duration of eight hours.
Millstone 1 Technical Specification 4.7.2.a states that the minimum test duration is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The licensee proposed a change to this technical specifi-cation on May 9, 1980.
The inspector stated that the minimum acceptable test duration would remain 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless a NRC licensing change authorizes a reduction in the length of test-time prior to the test.
The above items were discussed with the licensee's representatives.
The acceptability of the CILRT procedure is considered unresolved pending the licensee's action with regard to the above items. (245/80-19-01)
b.
Valve Line-up Review The inspector reviewed Appendix 0 to the CILRT draft procedure listing the required valve line-ups for conformance with requirements of the references above.
The problems identified are described below.
(1) The inspector was not able to verify adequate downstream vent
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paths for the head spray and atmosphere control systems.
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inspector discussed with representatives of the licensee the requirements for downstream venting to ensure the containment
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isolation valves are subjected to the test differential pressure.
The ifcensee's representative agreed to correct this problem and review all system line-ups for similar problems.
This item is unresolved.
(245/80-19-02)
(2) The Reactor Building Closed Cooling Water system (RBCCW) will be in operation during the CILRT.
Presently, this system is not covereo in the Local Leak Rate Test (LLRT) program.
The licensee's September 20, 1978 Appendix J submittal states that the applicable RBCCW valves (RC-6 and RC-15) are tested during the type A test.
The inspector discussed this matter with representatives of the licensee and stated that this item will be considered unresolved at this time pending licensee determination of the proper test method.
Resolution of this item will be required prior to perfor-mance of the 1980 CILRT. (245/80-19-03)
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6 (3) The drywell pressure switches form a containment boundary in a post accident environment.
The inspector noted that these pressure switches are isolated and vented during the Type A test.
The inspector discussed the need for full pressure testing of these penetrations.
This item is unresolved pending the licensee's determination of an acceptable test method. (245/80-19-04)
4.
Local Leak Rate Test (LLRT) Program References:
10 CFR 50 Appendix J Millstone 1 Surveillance Procedure 623.14, Revision 2, dated April 14, 1979 " Containment Isolation Valve Leak Rate Tests."
Millstone 1 10 CFR 50 Appendix J Submittals dated November 14, 1979, July 24, 1977, September 20, 1979.
The inspector reviewed the LLRT program at Millstone 1 using the references listed above.
The findings are summarized below:
a.
The licensee has addressed several issues developed during a previous inspection in this area (245/77-05).
The latest Appendix J testing program description submitted to NRR dated September 20, 1978 provides testing plans for all identified containment penetrations and intended plans for system modifications required to test the penetrations listed.
However, the licensee representative stated his position that no modification will be made until the NRC completes its review of the submittal.
The inspector stated that this matter is unresolved and will receive further NRC Management Review.
(245/80-19-05)
b.
The inspector noted several cases in SP 623.14 where proper venting and draining were not ensured prior to local leak rate testing (e.g.
Isolation Condenser System and Shutdown Cooling System).
This issue was initially raised during a previous inspection.
The inspector discussed this matter with representatives of the licensee and stated that Unresolved Item 245/77-05-06 would remain open pending licensee action to remove artificial leakage barriers in the local leak rate test program.
5.
Surveillance of Pipe Support and Restraint Systems The inspector reviewed the following procedures and records relating to pipe support and restraint surveillances for compliance with regulatory requirements.
Included is a summary of the findings.
During this review no unacceptable conditions were identified.
a.
PA 78-720 Calculation No. 78-720-107 GM, Rev. O., Millstone Unit No.
1, Operability Evaluation of The Safety Related Hydraulic Snubbers During Thermal Transients.
This engineering study was performed by the licensee and will be used to:
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- - evaluate the operability of alt safety related hydraulic snubbers in Millstone Unit No. 1,
- - recommend bleed and lock-up setting ranges for each snubber, and
- - develop an acceptable criteria for the snubbers including snubber piston extension requirements.
Based on the recommendations in this study the licensee has decided to remove and overhaul all snubbers that do not clearly meet the new bleed and lock-up setting ranges.
37 snubbers (29 Bergen-Patterson and 8 Grinnell) will be removed for overhaul.
The Itcensee will also perform surveillance as required by technical specifications (the first sample will be 9 out of a total of 88 snubbers).
b.
MP 7391.1 Hydraulic Shock Suppressor and Sway Arrester Repair, Rev. 4, 10/6/80.
This procedure has been revised to include the new bleed and lock-up setting ranges recommended in PA 78-720.
This procedure also includes temperature compensation criteria.
c.
Snubber Functional Test Records The inspector reviewed certification Test Records No. 44558-560, 598, 559, 588, 548, 512, 510, 579, 562, 563, 603, 565, 600 and 56f'.
These records document the overhaul of hydraulic snubbers performeo by Wylie Testing Laboratory during May,1979.
Records were found to be complete and all lock-up and bleed rates within prescribed limits.
The records selected for review represent approximately 20% of the total.
6.
Unresolved Items Unresolved items are items about which more information is required to determine whether they are acceptable or items of noncompliance.
Unresolved items are coetained in paragraphs 2, 3, and 4 of this report.
7.
Exit Interview The inspectors met with licensee representatives (denoted in paragraph 1)
at the conclusion of the inspection on October 9, 1980.
The inspectors summarized the scope and findings of the inspection at that time.
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