IR 05000289/1985018
| ML20209F889 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/27/1985 |
| From: | Bettenhausen L, Blumberg N, Wen P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20209F878 | List: |
| References | |
| 50-289-85-18, NUDOCS 8507120570 | |
| Download: ML20209F889 (5) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-289/85-18 Docket No.
50-289 License No.
DPR-50 Priority
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Category C
- Licensee: GPU Nuclear Corporation P. O. Box 480 Middletown, Pennsylvania 17057
- Facility Name: TMI-1 Inspection At: Middletown, Pennsylvania Inspection Conducted: May 28-31, 1985 Inspectors:
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P. C. Wen, Reactor Engine 4f
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emA6(A d3 /rc N. J. IMumberg, Lead Reap:tfr Eng',eer date
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Approved.by:
/h 8J L. H. Bettenhausen, Chief date
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Operations Branch, DRS Inspection Summary: Inspection on May 28-31, 1985 (Inspection Report No. 50-289/85-18).
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- Areas Inspected:
Licensee's actions on previous inspection findings, Restart Startup Test Program.
The inspection involved 56 inspection-hours onsite by two region based inspectors.
c Results: No violations were identified.
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DETAILS 1.0 Persons Contacted B. Ballard, Manager of QA, Modification / Operations
- T. Hawkins, Manager, Start-up and Test
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D. Hukill, Director, TMI-1 J. Pearce, Senior Staff Engineer
- C. W. Smyth, TMI-1 Licensing Manager
- R. J. Toole, Operations and Maintenance Director R. Tropasso, Nuclear Engineer W. S. Wilkerson, Lead Nuclear Engineer H. L. Wilson, Supervisor Preventative Maintenance U.S. NRC
- R. Conte, Senior Resident Inspector
.F. I. Young, Resident Inspector The inspector also contacted other licensee personnel during the inspec-tion.
- Denotes those present at the exit meeting on May 31, 1985.
2.0 Licensee Action on Previous Inspection Findings (Closed)~ Unresolved Item 289/84-07-03:
License Amendment 103 to TMI-1 Operating License requires that the licensee submit to NRC the results of the steam generator hot test program and a summary of its management
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review. The test result and summary of its management review were sub-mitted to NRC via GPU letters 5211-85-2099 (dated 05/28/85) and 5211-85-2095 (dated 5/21/85) respectively. The inspector reviewed the Kr-85 analysis result from Teledyne Isotopes Laboratory and the associated GPU leak rate calculation.
Results from this calculation are consistent with the results from off gas radiation monitors which were inspected in NRC inspection report: 289/85-16.
Based on the current Hot Function Test result, (test performed on April 10-19, 1985) the baseline OTSG primary to secondary leak rate is now determined to be 0.5 gph.
This item is closed.
(Closed) Licensing Action Item 83-0284:
The impact of NUREG-0630 Cladding Swell and Rupture Models results in more restrictive core operating
. limits during the first 31 Effective Full Power Day of Cycle 5 operation when reactor power levels are above 80%.
The inspector reviewed Test Procedure TP 800/1, " Controlling Procedure for Power Escalation",
Revision 0 and Surveillance Procedure SP 1301-9.8," Core Power Map Distribution", Revision 6.
The inspector noted that the revised operating limits has been incorporated in these procedures.
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This item is closed.
(Closed) Unresolved Item (50-289/84-23-02):
Several apparent deficiencies were observed concerning the test procedure used to perform the Waste Gas Disposal System leak check (SP 1309-11.29) performed on May 8, 1984.
Each apparent deficiency and the licensee's resolution are as follows:
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There was no information showing that the minimum concentration of tracer gas helium of 10 PPM stipulated by the procedure is adequate for the smallest leak rate detection.
The inspector verified that SP 1309-11.29 has been revised to require a concentration of helium of greater than 70 ppm. The calibration data for the mass spectrometer used was for helium standards of 10, 20 and 29 ppm. Actual concen-trations of helium in the tank were calculated to be greater than 15,000 ppm.
Based on the minimum concentration of helium required, the actual concentration used, and sensitivity of the instrument used, the inspector considers this issue resolved.
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Incorporate a reference to the specific helium mass spectrometer being used into the test procedure or incorporate a suitable test procedure into 1303-11.29.
The inspector verified that SP 1303-11.29 has been revised to reference ASTM E499-73, " Standard Methods of Testing For Sealer Using the Mass Spectrometer Leak In The Detector Probe Mode Method A-Direct Probing"; and that this method has been incorporated into SP 1303 11.29.
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The S.A.I contractor procedure which was used for May 8,1984 helium leak test of the wasu gas disposal system should be made available for inspection.
Procedure SAI-129-008, " Waste-Gas System Helium Testing Procedure", dated April 7, 1983 was reviewed by the inspec-tor. This is a generic procedure which must be integrated with a plant specific procedure such as SP 1303-11.29 and appear to be acceptable. As noted in the previous paragraph SP 1303-11.29 has been revised to incorporate the helium testing method within the
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scope of the procedure. The revised 1303-11.29 w4s used to perform the Waste Gas System leak test on March 14, 1985.
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Specific details of the qualifications of contractor testing person-nel who performed the May 8, 1984, helium mass spectrometer leak test of Waste Gas Disposal System were not available on site for review.
The contractor personnel who performed the May 8, 1984 were S.A.I; employees at that time. These personnel currently work for Utility Service Consultants Incorporated (USCI) and performed the March 14, 1985 test.
The inspector reviewed copies of certificates of qualifi-cation supplies by USCI certifying that the USCI test per'sonnel were qualified as level II Non-Destructive Test Examiners (NDE) from the period November 1, 1983 to November 1, 1986.
In addition a copy of the training and qualification program used by S.A.I. at the time
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the USCI personnel were employed there was reviewed by the inspector.
This program appeared to be comprehensive.
It should be noted the actual training and qualification records of all contractors are subject to periodic review by the licensee's vendor inspection program.
Procedure SP 1303-11.29 should provide acceptance criteria which
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defines the allowable measured leak rate which should not be exce-eded.
The acceotance criteria in the procedure reviewed in 1984 stated " cognizant engineers shall make the final determination as to the acceptance or rejection of the reported leakage...".
The pro-cedure has been revised to currently state the following "...the cogninizant engineer shall maka the final determination as to accept-
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ance or' rejection of the reported leakeage...The cognizant engineers determination shall be based on interpretation of the general cri-teria established in [GPUN Memorandum,..." Leak Reduction Program",
3310-84-170]..".
The _ leakage reduction program (LRP) specifies an acceptable range of
~I leak rates of 10-3 standard cubic centimeters per second to 10 (cc/s). A licensee representative stated that they did not want to place specific criteria directly in the procedure as this might encourage personnel to just meet an acceptable number and not reduce leakage to as low as practical.
He also noted that this was consis-tent with the philosophy of NUREG 0578 requires that all leakage be reduced to as low as prectical levels. The inspector did note that the LRP is now referred to by the procedure and does express an acceptable range.
The inspector reviewed test data from the leakage test performed on the Waste Gas System on March 14, 1985. All leakage identified was within'the acceptable range of the LRP; however, where leakage was
identified an exception and deficiency (B&D) report was written and attempts were made to reduce the leakage.
In each case the leakage was reduced to some lower level.
The inspector considers the reference to the LRP for acceptance criteria as an acceptable method, the review of the completed test procedure, test data, and E&D reports indicates the test personnel are meeting responsibility to reduce leakage to as low as practical levels.
Based on the above review of each item, the inspector considers the' licensee's resolution as acceptable.
This item is closed.
3.0 Reactor Startup Test Program The inspector reviewed the TMI-1 restart test program. Test procedure TP 700/1 " Low Power Physics Testing" will be the controlling logic for low power physics tests and natural circulation tests.
Test procedure TP
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800/1 " Controlling Procedure for Power Escalation" will serve as a con-trolling logic sequence for test and event performance during plant power escalation. Both procedures has been approved in accordance with plant administrative procedures.
The detailed review of the individual tests contained in the test sequence was completed and documented in previous inspection reports. No discrepancies were noted.
4.0 Quality Assurance Involvement in Startup Test The inspector discussed QA's rule in startup testing with QA manager. The inspector was told that QA/QC plans to verify prerequisite lists for plant heatup/ criticality.
In addition, QA/QC plans to have 24-hour coverage for the entire startup testing period.
The inspector had no further questions.
5.0 Exit Interview Licensee management was informed of the purpose and scope of the inspec-tion at the entrance interview. The findings of the inspection were periodically discussed and were summarized at the conclusion of the inspection en May 31, 1985. Attendees at the exit interview are denoted in paragraph 1.
No written material was provided to the licensee by the inspector at any time during this inspection.
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