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| {{Adams | | {{Adams |
| | number = ML20212K284 | | | number = ML20210C351 |
| | issue date = 07/31/1986 | | | issue date = 01/06/1987 |
| | title = Insp Repts 50-321/86-21 & 50-366/86-21 on 860714-18. Violation Noted:Failure to Perform Adequate Surveys for Effluent Releases | | | title = Discusses Analytical Results of Selected Radiochemical Analyses Submitted by ,As Suppl to Insp Repts 50-321/86-21 & 50-366/86-21.All Comparative Results in Agreement |
| | author name = Harris J, Stoddart P | | | author name = Brownlee V |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| | addressee name = | | | addressee name = Miller J |
| | addressee affiliation = | | | addressee affiliation = GEORGIA POWER CO. |
| | docket = 05000321, 05000366 | | | docket = 05000321, 05000366 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = 50-321-86-21, 50-366-86-21, NUDOCS 8608190364 | | | document report number = NUDOCS 8702090371 |
| | package number = ML20212K283 | | | title reference date = 11-24-1986 |
| | document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS | | | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE |
| | page count = 8 | | | page count = 6 |
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| | Georgia Power Company ATTN: Mr. J. H. Miller, J President P. O. Box 4545 Atlanta, GA 30302 Gentlemen: |
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| | SUBJECT: DOCKET N05. 50-321 AND 50-366, CONFIRMATORY MEASUREMENT RESULTS SUPPLEMENT TO INSPECTION REPORT NOS. 50-321/86-21 AND 50-366/86-21 As part of the NRC Confirmatory Measurements Program, spiked liquid samples were sent on September 22, 1986, to your facility for selected radiochemical analyse We are in receipt of your analytical results transmitted to us by your letter dated November 24, 1986, and the following comparison of your results to the known values are presented in Enclosure 1 for your information. The acceptance criteria for the comparisons are listed in Enclosure In our review of these data all comparative results were in agreement. These data should be reviewed in greater detail by cognizant staff members for any significant trends in the data among successive years in which samples have been analyzed by your facility. Any biases noted may be indicative of a programmatic weakness and your efforts sh.:uld be expended in determining reasons for such biase These results and any results from previous years pertaining to these analyses will be discussed at future NRC inspection |
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| | Sincerely, Virgil L. Brownlee, Chief Reactor Projects Branch 3 Division of Reactor Projects Enclosures: |
| UNITE D STATES NUCLEAR REGULATORY COMMISSION
| | 1. Confirmatory Measurement Comparisons Criteria for Comparing Analytical Measurements cc w/encls: (See page 2) |
| [ n- REGION 11 g j 101 MARIETTA STREET. '* t ATLANTA, GEORGI A 30323
| | 8702090371 e70106 PDR ADOCK 05000321 Q PDR v y |
| *%..... / AUG 0 61986
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| Report Nos.: 50-321/86-21 and 50-366/86-21
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| | Alabama Power Company 2 cc w/ enc 1: |
| Licensee: Georgia Power Company P. O. Box 4545 Atlanta, GA 30302 Docket Nos.: 50-321 and 50-366 License Nos.: DPR-57 and NPF-5 Facility Name: Hatch 1 and 2 Inspection Conducted: July 14-18, 1986 Inspector: h, b. hunh 7- M E b J.p. Harris ~ 0 ate Signed Accompanying Per nel: 4 L. Froemsdorf Approved by: N Yld P7 G. Tto301rt, Acting Section Chief Y[
| | J. P. O'Reilly, Senior Vice President Nuclear Operations J. T. Beckham, Vice President, Plant Hatch H. C. Nix, Site Operations General Manager A. Fraser, Acting Site QA Supervisor L. Gucwa, Manager, Nuclear Safety and Licensing B. C. Arnold, Chemistry Supervisor bcc w/ enc 1: |
| Date' Signed Division of Radiation Safety and Safeguards SUMMARY Scope: This routine, unannounced inspection was in the areas of review of the Radiochemistry Quality Control (QC) program organization and related procedures, QC records, calibration records, and comparison of the results of split samples analyzed by the licensee and NRC Region II mobile laborator Results: One violation was identified - Failure to perform adequate surveys for effluent release i 8608190364 860806 PDR ADOCK 05000321 Q PDR
| | NRC Resident Inspector Hugh S. Jordan, Executive Secretary Document Control Desk State of Georgia RII RII RII RII SAdamovitz JKahle DCollins e Algnatonis 12/ /86 12/ /86 12/ /86 12/ /86 |
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| | . JAN 0 A 1987 Gy rgia Power Company MITN: Mr. J. H. Miller, J President P. O. Box 4545 Atlanta, GA 30302 Gentlemen: y SUBJECT: DOCKET NOS. 50-348 AND 50-364, CONFIRMATORY MEASUREMENT RESULTS SUPPLEMENT TO INSPECTION REPORT NOS. 50-321/86-21 AND 50-366/86-21 As part of the NRC Confirmatory Measurements Program, spiked liquid samples were sent on September 22, 1986, to your facility for selected radiochemical analyse We are in receipt of your analytical results transmitted to us by your letter dated November 24, 1986, and the following comparison of your results to the known values are presented in Enclosure 1 for your informatio The acceptance criteria for the comparisons are listed in Enclosure In our review of these data all comparative results were in agreement. These data should be reviewed in greater detail by cognizant staff members for any significant trends in the data among successive years in which samples have been analyzed by your facility. Any biases noted may be indicative of a programmatic weakness and your efforts should be expended in determining reasons for such biase These results and any results from previous years pertaining to these analyses will be discussed at future NRC inspection ' |
| REPORT DETAILS Persons Contacted Licensee Employees B. C. Arnold, Chemistry Supervisor
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| *V. McGowan, Chemistry Supervisor J. M. Bray, Senior Quality Assurance Field Representative D. J. Elder, Senior Quality Assurance Field Representative -
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| B. Roberts, Laboratory Foreman, Chemistry G. Fuqua, Health Physics Specialist
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| *L. G. Byrnes, Senior Nuclear Engineer | |
| *W. B. Kirkley, Health Physics / Chemistry Engineering Supervisor
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| *C. R. Goodman, Regulatory Compliance Engineer
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| *T. L. Elton, Regulatory Compliance Supervisor
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| *K. B. Allison, Quality Assurance
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| *W. H. Rogers, Health Physics / Chemistry Superintendent
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| *A. Fraser, Quality Assurance Superintendent
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| *T. Greene, Deputy General Manager Other ifcensee employees contacted included several Health' Physics / Chemistry technician NRC Resident Inspectors
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| *P. Holmes-Ray
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| * Attended exit interview Exit Interview The inspection scope and findings were summarized on July 18, 1986, with those persons indicated in Paragraph 1 above. One violation (Paragraph 7)
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| concerning failure to make adequate surveys for radioactive material . in gaseous releases was discusse The inspector discussed areas for improvement in the laboratory QA program and the licensees commitment to evaluate the QA program. The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspectio . Radiochemistry Quality Control Program (84725)
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| The inspector reviewed selected portions of the Quality Assurance Program with cognizant licensee representatives and determined that organizational structure and program management had not changed significantly since the previous confirmatory measurements program (50-321/85-01, 50-366/85-01).
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| The inspector noted that some improvements in the QA program had been mad The licensee now participates in an interlaboratory comparison program with a vendor laboratory. However, the inspector identified several areas in the QA program that could be improved. The major observation was that the QA e
| | Sincerely, Virgil L. Brownlee, Chief Reactor Projects Branch 3 Division of Reactor Projects Enclosures: |
| | - Confirmatory Measurement Comparisons Criteria for Comparing Analytical Measurements cc w/encls: (Seepage 2) |
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| | Alabama Power Company 2 cg w/ encl: |
| | t(. P. O'Reilly, Senior Vice President uclear Operations T. Beckham, Vice President, Plant H&tch |
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| | . C. Nix, Site Operations General |
| | , , Manager |
| | %. Fraser, Acting Site QA Supervisor W. Gucwa, Manager, Nuclear Safety lI.andLicensing C. Arnold, Chemistry Supervisor bec w/ encl: |
| | MCResidentInspector t%gh S. Jordan, Executive Secretary Document Control Desk State of Georgia r |
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| | RII RII RI RII SAdamovitz JKahle FCantrell 12/ /90 4E P /86' DCollins*\<g9 1$/5/86 i . |
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| program is segmented with no clear mechanism to provide an integrated look at all the elements in the program. The intercomparison studies are handled by one individual, the daily check trends are handled by the gamina spectroscopy computer and only provides warning flags if a parametec is out of bounds, and different aspects of calibrations are handled by different peopl Divisions between QA elements such as these reduce the possibilities of detecting and correcting adverse ~ measurement performance before serious deficiencies aris The inspector noted that calibration records can be difficult to recover from the licensee document / records control system. The data for the current calibrations were recovered but not for the previous calibrations. The inspector found that for some geometries, records showed that confirmations were made of the new detector efficiencie Though not required by the written calibration procedures, such confirmations are considered good laboratory practice and, if done, they should be performed consistently for all possible geometries. The inspector was informed that the QA program is being reviewed by the corporate office to develop a uniform laboratory QA program for Hatch and Vogtle. The licensee agreed to evaluate the current QA program for improvements in regard to the inspector's comments. The results of this evaluation will be- reviewed in a subsequent inspection (IFI 50-321/86-21-01).
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| No violations or deviations were identifie . Audits (84725)
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| Technical Specification 6.5.2.8 requires that audits of activities shall be performed encompassing the conformance of unit cperations to provisions contained within the Technical Spacifications and license conditions at least once per 12 months, the Radiological Environmental Monitoring Program at least once per 12 months, and the Offsite Dose Calculation Manual and the Process Control Program at least once per 24 months. The inspector reviewed the following audit reports:
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| QA Audit 85-SC-1, Qualification / Training Technical Specification Surveillances (Chemistry Program), February 1985 QA Audit 85--SC-2, Sampling, Laboratory Activities, Quality Assurance /
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| Quality Control Program, May 1985 QA Audit 85-SC-3, Routine Radiochemistry Practices - Laboratory, Count Room, Post Accident Sampling System, September 1985 QA Audit 85-SC-4, Hazardous Substance Control, December 1985 QA Audit 86-SC-1, Quality Assurance / Quality Control Program, Reactor Feedwater Chemistry, Auxiliary Feedwater Chemistry, Records and Reports, April 1986 The inspector noted that the Site QA staff has personnel on the staff with expertise in the subject area. Additional personnel resources are available through the corporate office, other Georgia Power facilities, and contractors. The audits appeared to be thorough and programmatic in natur i f, .
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| The inspectof discussed the overall audit program and reviewed responses to audit findings with cognizant licensee personnel. The audit program addresses short - tern and long term corrective action Mechanisms and managerhent. support exist for the QA department to pursue additional corrective action if dissatisfied with proposed corrective action No violations or deviations were identifie S. Procedures (84725)
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| Technical Specification 6.8.1 requires written procedures to be established, implemen t.ed , and maintaine The inspector selectively reviewed the folicwing procedures. All procedures listed had been reviewed and approved as rcquired, CI-0CB-007-0, Internal Gas Flow Proportional Counter (NMC), Rev. O, June 11, 1985 CI-0CG-008-0, Well Counter System, Rev. O, June 11, 1985 P.CI-0CG-010-0, Grmma Spectrometer System Ge(L1), Rev. O, June 11, 1985 CI-0CB-021-0, EC&G Ortec Model 576 Dual Alpha Spectrometer, Rev. O, June 11, 1985 CH-SAM-010 0, Routiae Reactor Coolant Grab Sanipling, Rev. O, June 1, 1985 G2Cll-SAM-Oll-0, Routine Reactor Coolant Diluted Grab Sampling, Rev. O, June 1, 1985 CH-Salt-012-CS, Routine Drywell Atmosphere Grab Sampling, Rev. 1, March 1, 1986 CH-SAM-013-OS, Routine Drywell Atmosphere Diluted Grab Sampling, Rev. O, March 1, 1986 C,4-SAM-014-0, Post Accident Reactor Coolant Diluted Grab Sampling, Rev. O, June 11, 1985 CH-SAM-015-05, Post Accident Reactor Coolant Grab Sampling, Rev.1,
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| ,luly 1, 1985 CI-CAL-002-0N, Laboratory Instrument Calibration and Preventative Maintenance, Rev. 1, November 18, 1985 CI-0PS-004-0, Gas Vial Sampler, Rey. O, June 11, 1985 CH-QCX-001-05, Quality Centrol for Chemical Analysis, Rev. 2, <
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| Febroary 28, 1986 CH-RCL-001-0, Strontiun Determination, Rev. O, June 11, 1985 m
| | ENCLOSUftE 1 -) |
| | | CONFIRMATORY MEASUREMENT COMPARIS006S OF FE-55 ANALYSIS FOR HATCH NUCLEAR PLANT ON SEPTEM8ER 22, 1986 |
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| | . MRC Ratio Licensee (Licensee /NRC) yp_a ri son C |
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| | Samste ID fuCi/onit) ' fuCi/ unit) Resolution 52 0.92 Agreement H-3 2. f4 E-5 2.60 i .05 E-5 48 1.19 Agreement Fc-55 2.3 E-5 1.93 i .084 E-5 |
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| | .76 Ag reement Sr-89 2.5 E-5 3.27 i .10 E-5 33 26 1.07 Agreement S r-90 3.3 E-6 3.09 i .12 E-6 |
| 4 CH-RCL-002-0, Iodine and Particulate Release Monitoring, Rev. 1, November 29, 1985 CH-RCL-003-0, Gaseous Release of Tritium, Rev.1, December 5,1985 CH-RCL-005-0, Preparation of Samples for Counting, Rev. O, June 11, 1985 CH-RCL-013-0, Gaseous Waste Sample Analysis, Rev.1, November 29, 1985 CH-SAM-002-0, Sampling of Process Streams for Laboratory Analysis, Rev. O, June 11, 1985 CH-RCL-015-0, EPA Crosscheck Program, Rev. O, June 11, 1985 HI-0CB-064-0S, Tennelec LB 5100-1 and APC System Operation and b Calibration, Rev. O, April 14, 1986 CH-CAL-003-0, Radioactive Standards Preparation, Rev. O, December 5, 1985 CI-0CB-036-0S, Nuclear Data Gamma Spectrometer System, Rev. O, July 1, 1986 No violations or deviations were identifie . Records (84725)
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| The inspector reviewed selected portions of the following reccrds: Tennelec LB 5100 No. D31-N139, Daily Calibration Data for January -
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| July 1986 including:
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| (1) Alpha / Beta Performance Checks (2) Alpha / Beta Trend Charts (3) Alpha / Beta Background Data NMC Internal Gas Flow Proportional Counter No. D31-N003 Daily Calibration Data for January - July 1986 including: | |
| (1) Alpha / Beta Source Checks (2) Alpha / Beta Background Data (3) Efficiency Determination (4) Dead-time Test Results (5) Alpha Results Well Counter Nos. D31-N121 & 031-N122 Daily Calibration Data for i January - July 1986 including:
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| (1) Daily Calibration Checks (2) Background Checks
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| W 5 , Gamma Spectroscopy Detector System Nos. 1, and 2 1986 Efficiency Calibration Records for the following geometries: 14 cc gas vial, 47 mm millipore filter, charcoal cartridge, 50 mi bottle, and liter marinelli beaker, Gaseous Release Permits December 1985 - July 1986 No violations or deviations were identifie . Confirmatory Measurements (84725)
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| During the inspection, reactor coolant and selected plant effluent / process streams were sampled and analyzed for radionuclide concentrations using the licensee and NRC Region II Mobile Laboratory gamma ray spectroscopy system ,
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| The purpose of these comparative measurements was to verify the licensee's ability to measure radionuclides accurately in various plant systems and effluent streams. Licensee's counting geometries studied included the following: 1000 cc liquid marinelli, 1000 cc gas marinelli, 14 cc gas vial, -
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| 50 mi bottle, 47 ml millipore particulate filter and charcoal cartridg Comparisons of licensee and NRC results are listed in Table 1 with the acceptance criteria given in Attachment The results showed agreement for the 50 m1 bottle, particulate filter, 14 cc gas vial, and 1000 cc liquid marinelli geometry. Three of five isotopes showed agreement for the 50 m1 bottle geometry, but a review of the calibration data and other validation checks indicate that the calibration was adequate. The inspector noted that there was some difficulty with the sample split s For the charcoal cartridge geometry, the inspector noted a high bias (>20%)
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| in the analysis for both detectors with one detector system in disagreemen This discrepancy could not be accounted for during the inspector's revie The results for the 1000 cc gas marinelli was in disagreement, biased high compared to the NRC results. Upon investigation, the inspector questioned the volume used for this geometry and requested the licensee to verify the volume for this geometry and the 14 cc gas vial. The licensee informed the inspector that 1000 cc had been used for approximately one year. The licensee's volume verification indicated an actual volume of approximately 1250 cc. This accounts for some of the problems noted in the disagreement between the licensee's measuremetits using this geometry, versus the NRC's measurement The inspector informed the licensee that this would be considered a violation; failure to make adequate surveys (50-321/86-02, 50-366/86-02). The inspector also noted that though agreement was obtained with the 14 cc gas vial geometry, the licensee used a 14 cc volume when the verified volume was approximately 14.5 c One violation was identified - failure to make adequate survey .
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| TABLE 1 RESULTS OF CAMMA-SPECTROSCOPY CONFIRMATORY MEASUREMENTS AT E. 1. HATCH NUCLEAR POWER PLANT JULY 14-18, 1986 CONCENTRATION RATIO
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| SAMPLE ISOTOPE LICENSEE NE RESOLUTION LICt NSEE/NRC COMPARISON (2) Reactor Coolant 1-132 8.81 E-4 1.33 .082 E-3 16 .66 D i sa g reement (50 mi bottle) 1-133 3.38 E-4 5.19 i .374 E-4 14 .65 Ag reemen t 1-134 2.56 E-3 5.91 i .516 E-3 12 .43 D i sag reemen t Tc-99m 1.27 E-2 1.44 i .008 E-2 180 .88 Ag reement Mn-56 2.08 E-3 2.77 i .110 E-3 25 .75 Ag reement (2) Liquid Waste 1-131 3.58 E-7 4.57 i .613 E-7 7 .78 Ag reemen t (1 L Ma ri ne l l i ) 1-133 7.42 E-7 9.16 1 1.26 E-7 7 .81 Ag reemen t Cs-137 8.38 E-7 7.74 i .780 E-7 10 1.08 Ag reemen t (1) Spiked Ba-133 5.26 E-2 4.00 t .031 E-2 129 1.32 D i sag reement Cha rcoa l Ca rt ridge (2) Spiked Ba-133 4.78 E-2 4.00 t .031 E-2 129 1.20 Ag reement Cha rcoa l Ca rt ridge (1) Spiked Co-60 9.32 E-3 9.12 i .184 E-3 50 1.02 Ag reemen t Pa rticulate Fil ter Cs-137 1.36 E-2 1.28 i .017 E-2 75 1.06 Ag reement (2) Spiked Co-60 8.7 E-3 9.12 i .184 E-3 50 .95 Ag reemen t Pa rticulate Filter Cs-137 1.24 E-2 1.28 i .017 E-2 75 .97 Ag reemen t (1) Pretreatment Cas K-87 1.40 E-3 2.28 1 .096 E-3 24 .61 *
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| D i sag reement 14 cc vial K-88 7.23 E-4 9.19 i .689 E-4 13 .79 Ag reemen t Xo-135 9.94 E-4 8.96 i .228 E-4 39 1.11 Ag reemen t (1) Post-t rea tment Ca s Xe-133 3.37 E-3 2.09 ! .097 E03 22 1.62 D i sa g reement 1250 cc Ma rinelli Xo-135 7.43 E-3 3.37 1 .075 45 2.20 D i sa g rooment
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| ATTACHMENT 1 CRITERIA FOR COMPARING ANALYTICAL MEASUREMENTS This attachment provides criteria for comparing results of capability tests and verification measurements. The criteria are based on an empirical relationship which combines prior experience and the accuracy needs of this progra In these criteria, the judgement limits are variable in relation to the comparison of the NRC's value to its associated uncertainty. As that ratio, referred to in this program as " Resolution," increases, the acceptability of a licensee's measurements should be more selective. Conversely, poorer agreement must be considered acceptable as the resolution decrease RATIO = LICENSEE VALUE NRC REFERENCE VALUE Resolution Agreement
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| <4 0.4 - .5 - .6 - 1.66 16 - 50 0.75 - 1.33 51 - 200 0.80 - 1.25
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| >200 0.85 - 1.18
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| | ; ,y ENCLOSURE Criteria for Comparing Analytical Measurements This enclosure provides criteria for comparing results of capability tests and verif' cation measurements. The criteria are based on an empirical relationship which combines prior experience and the accuracy needs of this progra In these criteria, the judgement limits denoting agreement or disagreement between licensee and NRC results are variable. This variability is a function of the NRC's value relative to its associated uncertainty, referred to in this program as " Resolution"2 increases, the range of acceptable differences between . |
| | the NRC and licensee values should be more restrictive. Conversely, poorer agreement between NRC and licensee values must be considered acceptable as the resolution decrease For comparison purposes, a ratio r of the licensee value to the NRC value for each individual nuclide is computed. This ratio is then evaluated for agreement based on the calculated resolution. The corresponding resolution and calculated ratios which denote agreement are listed in Table .1 below. Values outside of the agreement ratios for a selected nuclide are considered in disagreemen " Resolution = NRC Reference Value for a Particular Nuclide ' |
| | Associated Uncertainty for the Value |
| | ' Comparison Ratio = Licensee Value NRC Reference Value Confirmatory Measurements Acceptance Criteria Resolutions vs. Comparison Ratio Comparison Ratio |
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| | for Resolution Agreement |
| | <4 0.4 - .5 - .6 - 1.66 16 - 50 0.75 - 1.33 51 - 200 0.80 - 1.25 |
| | >200 0.85 - 1.18 |
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Forwards Insp Repts 50-321/99-04 & 50-366/99-04 on 990530-0710.One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy
ML20210J9501999-08-0202 August 1999
Forwards SER Finding Licensee Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Edwin I Hatch Nuclear Plant,Units 1 & 2
ML20210J9021999-08-0202 August 1999
Forwards SER Finding Licensee Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Edwin I Hatch Nuclear Plant,Units 1 & 2
HL-5814, Forwards New Relief Requests for Third 10-year Interval Inservice Insp Program for Ei Hatch Nuclear Plant.New Relief Requests Were Developed to Propose Alternate Insps & to Allow Use of ASME Code Cases N-605,N-508-1,N-323-1 & N-5281999-07-30030 July 1999
Forwards New Relief Requests for Third 10-year Interval Inservice Insp Program for Ei Hatch Nuclear Plant.New Relief Requests Were Developed to Propose Alternate Insps & to Allow Use of ASME Code Cases N-605,N-508-1,N-323-1 & N-528
05000366/LER-1999-007, Forwards LER 99-007-00 Re Personnel Error & Inadequate Corrective Action Causing Automatic Reactor Shutdown1999-07-27027 July 1999
Forwards LER 99-007-00 Re Personnel Error & Inadequate Corrective Action Causing Automatic Reactor Shutdown
ML20210E1601999-07-20020 July 1999
Forwards Insp Repts 50-321/99-10 & 50-366/99-10 on 990616-25.One Violation Noted Being Treated as Ncv.Team Identified Lack of Procedural Guidance for Identification & Trending of Repetitive Instrument Drift & Calibr Problems
HL-5810, Forwards Rev 17B to Ei Hatch FSAR & Rev 14B to Fire Hazards Analysis & Fire Protection Program, for Plant.Encls Reflect Changes Made Since Previous Submittal.With Instructions1999-07-15015 July 1999
Forwards Rev 17B to Ei Hatch FSAR & Rev 14B to Fire Hazards Analysis & Fire Protection Program, for Plant.Encls Reflect Changes Made Since Previous Submittal.With Instructions
HL-5808, Forwards Ei Hatch Nuclear Plant,Unit 1 Extended Power Uprate Startup Test Rept for Cycle 19. Rept Summarizes Startup Testing Performed on Unit 1 Following Implementation of Extended Uprate During Eighteenth Refueling Outage1999-07-15015 July 1999
Forwards Ei Hatch Nuclear Plant,Unit 1 Extended Power Uprate Startup Test Rept for Cycle 19. Rept Summarizes Startup Testing Performed on Unit 1 Following Implementation of Extended Uprate During Eighteenth Refueling Outage
HL-5807, Estimates That Seventeen (17) Submittals Will Be Made During Fy 2000 & Two (2) Submittals Will Be Made During Fy 2001,in Response to Administative Ltr 99-02, Operating Reactor Licensing Action Estimates1999-07-14014 July 1999
Estimates That Seventeen (17) Submittals Will Be Made During Fy 2000 & Two (2) Submittals Will Be Made During Fy 2001,in Response to Administative Ltr 99-02, Operating Reactor Licensing Action Estimates
ML20210J1091999-07-10010 July 1999
Submits Suggestions & Concerns Re Y2K & Nuclear Power Plants
HL-5804, Informs NRC That on or After 991018,SNOC Plans to Begin Storing Spent Fuel in Ei Hatch ISFSI IAW General License Issued,Per 10CFR72.2101999-07-0909 July 1999
Informs NRC That on or After 991018,SNOC Plans to Begin Storing Spent Fuel in Ei Hatch ISFSI IAW General License Issued,Per 10CFR72.210
HL-5796, Forwards Response to NRC 990331 Request for Supplemental Info Re SNC Earlier GL 95-07 Responses.Gl 95-07 Evaluation Sheets for Units 1 & 2 RHR Torus Spray Isolation Valves Are Encl1999-07-0909 July 1999
Forwards Response to NRC 990331 Request for Supplemental Info Re SNC Earlier GL 95-07 Responses.Gl 95-07 Evaluation Sheets for Units 1 & 2 RHR Torus Spray Isolation Valves Are Encl
HL-5801, Forwards New Relief Requests for Third 10-Yr Interval ISI Program for Ei Hatch Nuclear Plant.New Relief Requests RR-25 & RR-26 Were Developed to Propose Alternate Repair Techniques IAW ASME Code N-562 & N-561,respectively1999-07-0909 July 1999
Forwards New Relief Requests for Third 10-Yr Interval ISI Program for Ei Hatch Nuclear Plant.New Relief Requests RR-25 & RR-26 Were Developed to Propose Alternate Repair Techniques IAW ASME Code N-562 & N-561,respectively
ML20209E4801999-06-30030 June 1999
Confirms 990630 Telcon Between M Crosby & DC Payne Re Arrangements Made for Administration of Licensing Exam at Plant During Weeks of 991018-1101
ML20196H8811999-06-25025 June 1999
Forwards Insp Repts 50-321/99-03 & 50-366/99-03 on 990418- 0529.No Violations Occurred.Conduct of Activities at Plant Generally Characterized by safety-conscious Operations & Sound Engineering & Maint Practices
HL-5790, Responds to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants1999-06-21021 June 1999
Responds to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants
ML20212J0541999-06-17017 June 1999
Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First
ML20207E7561999-06-0303 June 1999
Informs of Completion of Review & Evaluation of Info Provided by Southern Nuclear Operating Co by Ltr Dtd 980608, Proposing Changes to Third 10-Yr Interval ISI Program Plan Requests for Relief RR-4 & R-6.Requests Acceptable
HL-5763, Informs That Util Is Changing Responsibility for Periodic Concerns Program Review,Per Insp Repts 50-321/95-12 & 50-366/95-12.Reviews Will Now Be Performed Under Direction of Vice President & Corporate Counsel1999-05-20020 May 1999
Informs That Util Is Changing Responsibility for Periodic Concerns Program Review,Per Insp Repts 50-321/95-12 & 50-366/95-12.Reviews Will Now Be Performed Under Direction of Vice President & Corporate Counsel
HL-5785, Forwards New Relief Requests RR-V-16 for Third 10-yr Interval Inservice Testing Program for Ei Hatch Nuclear Plant.Relief Request Was Developed to Propose Alternate Schedule for Replacement of HPCI Rupture Disks1999-05-18018 May 1999
Forwards New Relief Requests RR-V-16 for Third 10-yr Interval Inservice Testing Program for Ei Hatch Nuclear Plant.Relief Request Was Developed to Propose Alternate Schedule for Replacement of HPCI Rupture Disks
ML20206Q0751999-05-0606 May 1999
Forwards Insp Repts 50-321/99-02 & 50-366/99-02 on 990307-0417.No Violations Noted
ML20206G1611999-05-0404 May 1999
Forwards SER Approving Util 990316 Revised Relief Request RR-P-14,for Inservice Testing Program for Pumps & Valves Pursuant to 10CFR50.55a(a)(3)(ii)
ML20206P6921999-04-27027 April 1999
Discusses 990422 Public Meeting at Hatch Facility Re Results of Periodic Plant Performance Review for Hatch Nuclear Facility for Period of Feb 1997 to Jan 1999.List of Attendees & Copy of Handouts Used by Hatch,Encl
HL-5777, Notifies NRC That Exam Coverage for One Weld Exceeded Criteria for Plant.Reasons for Exam Coverage Being Less than Initially Estimated as Listed1999-04-26026 April 1999
Notifies NRC That Exam Coverage for One Weld Exceeded Criteria for Plant.Reasons for Exam Coverage Being Less than Initially Estimated as Listed
HL-5758, Forwards Response to NRC 990129 RAI Re GL 96-05 Program at Ei Hatch Nuclear Plant1999-04-0909 April 1999
Forwards Response to NRC 990129 RAI Re GL 96-05 Program at Ei Hatch Nuclear Plant
ML20205T1831999-04-0909 April 1999
Informs That on 990316,S Grantham & Ho Christensen Confirmed Initial Operator Licensing Exam Schedule for Ei Hatch NPP for FY00.Initial Exam Dates Are 991001 & 2201 for Approx 12 Candidates.Chief Examiner Will Be C Payne
ML20205M3181999-04-0707 April 1999
Confirms Telcon Between D Crowe & Ph Skinner Re Mgt Meeting Scheduled for 990422 in Conference Room of Maint Training Bldg.Purpose of Meeting to Discuss Results of Periodic PPR for Plant for Period of Feb 1997 - Jan 1999
ML20205M3011999-04-0202 April 1999
Forwards Insp Repts 50-321/99-01 & 50-366/99-01 on 990124-0306.Non-cited Violation Identified
HL-5761, Forwards Revised Ei Hatch Nuclear Plant Psp,Effective 990331,per 10CFR50.54(p)(2).Justification & Detailed Instructions Encl.Plan Withheld,Per 10CFR73.211999-03-31031 March 1999
Forwards Revised Ei Hatch Nuclear Plant Psp,Effective 990331,per 10CFR50.54(p)(2).Justification & Detailed Instructions Encl.Plan Withheld,Per 10CFR73.21
HL-5750, Forwards Status of Decommissining Funding,Per Requirements 10CFR50.75(f)(1),on Behalf of Licensed Owners of Ei Hatch Nuclear Plant1999-03-30030 March 1999
Forwards Status of Decommissining Funding,Per Requirements 10CFR50.75(f)(1),on Behalf of Licensed Owners of Ei Hatch Nuclear Plant
ML20205H1491999-03-25025 March 1999
Forwards Info for OLs DPR-7 & NPF-5 Re Financial Assurance Requirements for Decommissioning Nuclear Power Reactors,Per 10CFR50.75(f)(1).Municipal Electric Authority of Georgia Is One of Licensed Owners of Ei Hatch,Owning 17.7% of Facility
ML20205D3211999-03-24024 March 1999
Informs That Safety Sys Engineering Insp Previously Scheduled for 990405-09 & 19-23,rescheduled for 990607-11 & 21-25
1999-09-24
[Table view]
Category:NRC TO UTILITY
MONTHYEARML20062G6171990-11-19019 November 1990
Forwards Insp Repts 50-321/90-22 & 50-366/90-22 on 901015- 19.No Violations or Deviations Noted
ML20062F8171990-11-14014 November 1990
Forwards Insp Repts 50-321/90-20 & 50-366/90-20 on 900915- 1020 & Notice of Violation
ML20058H8421990-11-13013 November 1990
Forwards Insp Repts 50-321/90-21 & 50-366/90-21 on 901001- 05.No Violations or Deviations Noted
ML20217A2921990-11-13013 November 1990
Advises That Kn Jabbour Assigned as Project Manager for Plant
ML20217A7441990-11-0707 November 1990
Forwards Insp Repts 50-321/90-16 & 50-366/90-16 on 901001-12.No Violations or Deviations Noted
ML20058E8491990-10-23023 October 1990
Forwards Insp Repts 50-321/90-19 & 50-366/90-19 on 900925-28.No Violations or Deviations Noted
ML20062B2461990-10-12012 October 1990
Requests That Analyses of Liquid Samples Spiked W/ Radionuclides Be Completed as Soon as Practicable,But No Later than 60 Days from Receipt of Samples.Results Should Be Sent to DM Collins at Listed Address
ML20059J9151990-09-0707 September 1990
Forwards Guidance for Reporting of Events Under Requirements of 10CFR50.73.W/o Encl
ML20058M3561990-08-0808 August 1990
Discusses Util Response to Generic Ltr 89-10, Safety- Related Motor-Operated Valve (MOV) Testing & Surveillance. Recommends That Licensees Test MOVs in Situ Under Design Basis Conditions
ML20058L5031990-08-0303 August 1990
Advises That 900727 Response to Generic Ltr 88-14 Re Instrument Air Supply Sys Problems Affecting safety-related Equipment,Acceptable
ML20055H3581990-07-23023 July 1990
Advises That Util Provided Acceptable Resolution to NRC Bulletin 89-001, Failure of Westinghouse Steam Generator Tube Mechanical Plugs
ML20055H6451990-07-13013 July 1990
Forwards Insp Repts 50-321/90-14 & 50-366/90-14 on 900512-0622.No Violations or Deviations Noted
ML20055E8841990-07-10010 July 1990
Advises That EAS-28-0589, Edwin I Hatch Nuclear Plant Basis for Use of Homogeneous Equilibrium Model for Environ Qualification & Radiological Release Evaluation, Withheld from Public Disclosure (Ref 10CFR2.790),per 900628 Request
ML20055H3451990-06-21021 June 1990
Responds to Re Basis for Employment Action Involving Former Util Employee Reporting Safety Concerns. Concurs W/Request to Defer Further Discussion Until Completion of Dept of Labor Process
ML20059M9561990-06-13013 June 1990
Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl
ML20055D0021990-06-11011 June 1990
Discusses Util 900514 Application for Amend to License NPF-47,increasing Suppression Pool Temp from 95 F to 100 F. Requests That Util Demonstrate Applicability of Items Addressed in Encl Hatch Safety Evaluation to Facility
ML20055C5131990-05-17017 May 1990
Authorizes Restart of Facility When Identified Flaws in Welds Repaired W/Overlay Designs,Per Util & Generic Ltr 88-01.Full Rept of outage-related Insp Activities Should Be Submitted Following Restart
ML20055C4771990-05-11011 May 1990
Forwards Insp Repts 50-321/90-13 & 50-366/90-13 on 900430-0504.No Violations or Deviations Noted
ML20248D1821989-09-20020 September 1989
Forwards Insp Repts 50-321/89-16 & 50-366/89-16 on 890722- 0825.Violations Noted But Not Cited Since All Criteria of licensee-identified Violations Met
ML20248G9731989-09-20020 September 1989
Forwards Unexecuted Amend 13 to Indemnity Agreement B-69, Reflecting Increase in Primary Layer of Nuclear Energy Liability Insurance Provided by ANI & Maelu
ML20247C9281989-09-0606 September 1989
Forwards Exam Rept 50-321/OL-89-01 Administered on 890612-16.Concerns Raised Re pre-exam Review Ineffective in Ensuring site-specific Exam Validity & Operator Generic Weaknesses
ML20247B3931989-09-0505 September 1989
Forwards Insp Repts 50-321/89-17 & 50-366/89-17 on 890612-16 & 0731-0804.No Violations or Deviations Noted
ML20247B5381989-09-0101 September 1989
Forwards Insp Repts 50-321/89-18 & 50-366/89-18 on 890807-11.Violation Noted But Not Cited,Based on Meeting Criteria of licensee-identified Violations
ML20246E6861989-08-24024 August 1989
Advises That 890807 Rev to Guard Training & Qualification Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable for Inclusion Into Plan
ML20246M8791989-08-23023 August 1989
Forwards Insp Repts 50-321/89-13 & 50-366/89-13 on 890710-13.Violations Noted
ML20246P4921989-08-22022 August 1989
Forwards Insp Repts 50-321/89-15 & 50-366/89-15 on 890724-28.No Violations or Deviations Noted
ML20246N8001989-08-18018 August 1989
Forwards Insp Repts 50-321/89-08 & 50-366/89-08 on 890515-19,0605-09 & 19 & Notice of Violation.Concern Raised Re Implementation of Inservice Testing of Pumps & Valves on Emergency Diesel Generator Sys
ML20246C9721989-08-16016 August 1989
Advises That Apr 1989 Rev 9 to Emergency Plan Meets Planning Stds of 10CFR50.47(b) & Requirements of 10CFR50,App E
ML20246A6621989-08-0808 August 1989
Forwards Insp Repts 50-321/89-14 & 50-366/89-14 on 890717-20.No Violations or Deviations Noted
ML20248C9041989-08-0202 August 1989
Forwards Insp Repts 50-321/89-12 & 50-366/89-12 on 890624-0721.Violations Noted.Violation Not Being Cited Due to Licensee Meeting All of Criteria for Categorization of licensee-identified Violations
ML20248A2941989-08-0101 August 1989
Discusses Util Compliance W/Atws Rule (10CFR50.62).Design Change to Utilize Test Switches to Block Actuation Signal to Alternate Rod Injection Solenoid Valve During Testing Acceptable
ML20247N7801989-07-27027 July 1989
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-321/88-37 & 50-366/88-37.Violation Occurred as Stated in Notice of Violation.Assessment Withheld (Ref 10CFR73.21)
ML20247E6181989-07-24024 July 1989
Informs of Agreement Reached During 890719 Telcon Re IGSCC Exam for Fall 1989 Refueling/Maint Outage & Matter of Calibr Blocks to Be Used for Ultrasonic Insp Activities During Outage
ML20247E4251989-07-19019 July 1989
Requests Listed Items for Reactor Operator & Senior Operator Licensing Exams Scheduled for Wk of 891009.All Reactor Operator & Senior Reactor Operator License Application Info Should Be Submitted at Least 30 Days Before First Exam Date
ML20247B0761989-07-19019 July 1989
Ack Receipt of Util Withdrawing 880711 Request for Relief from ASME Code Section XI Requirement for Testing Class 2 Portions of Main Steam Lines of Units at 1.25 Times Design Pressure.Code Case N-479 Acceptable for Use at Plant
IR 05000321/19890021989-07-17017 July 1989
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-321/89-02 & 50-366/89-02
ML20247E3651989-07-17017 July 1989
Requests Listed Items for Requalification Program Evaluation Scheduled for Wks of 890911 & 25.NRC to Administer Operating & Written Exams & Discuss W/Qualified Personnel & Operators Schedule for Processing Exams.Ref Matl Requirements Encl
ML20246Q2511989-07-14014 July 1989
Forwards Insp Repts 50-321/89-11 & 50-366/89-11 on 890619-23.Noted Violations Not Being Cited Due to Criteria for Categorization of Licensee Identified Violations Being Met
ML20247P5571989-07-13013 July 1989
Documents Info Received During Discussions Between Region II Personnel & Concerned Individual.Encl Withheld (Ref 10CFR2.790(a))
ML20246F6661989-07-0606 July 1989
Affirms Validity of Staff Reaction to Final Rept,Submitted in Util Re Bent Rockbolts Observed in Torus Anchorage.Bent Rockbolts Appear to Pose No Safety Impediment to Restart.Issue Closed
ML20246K7441989-07-0505 July 1989
Forwards Insp Repts 50-321/89-10 & 50-366/89-10 on 890527- 0623.Details Re Licensee non-cited Violations Described in Rept
ML20246B6351989-06-30030 June 1989
Forwards NRR Ack Receipt of Petition Filed by Ecology Ctr of Southern California,For Info.Ltr States That Petition Being Treated Under 10CFR2.206 of Commission Regulation
ML20245K9301989-06-23023 June 1989
Advises That Apr 1989 Rev to Physical Security Plan Transmitted by Consistent W/Provisions of 10CFR50.54(p) & Acceptable
ML20245J9641989-06-22022 June 1989
Advises That Util 880224 Rev 2 to Inservice Insp Program for Second 10-yr Interval Acceptable Except as Noted in Encls
ML20245H7291989-06-19019 June 1989
Forwards Insp Repts 50-321/89-07 & 50-366/89-07 on 890422-0526.Licensee Identified Violations Not Cited
ML20245D4541989-06-15015 June 1989
Forwards Insp Repts 50-321/89-02 & 50-366/89-02 on 890227-0317 & Notice of Violation
ML20245A9991989-06-14014 June 1989
Forwards Insp Repts 50-321/89-09 & 50-366/89-09 on 890522-26.No Violations or Deviations Noted
ML20248C1331989-06-0606 June 1989
Forwards Director'S Decision 89-03,transmittal Ltr & Fr Notice Denying Ocre Petition Filed Under 10CFR2.206 for Commission Take Action Applicable to All Bwrs,Per 890309 Power Oscillation Event at LaSalle Unit 2
ML20244D1581989-06-0505 June 1989
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-321/89-06 & 50-366/89-06
1990-09-07
[Table view]
Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217D2901999-10-13013 October 1999
Forwards SER Accepting Licensee 990305 Proposed Changes to Edwin I Hatch Nuclear Plant Emergency Classification Scheme to Add Emergency Action Levels Related to Operation of Independent Spent Fuel Storage Installation
ML20217G0401999-10-0707 October 1999
Forwards Insp Repts 50-321/99-09 & 50-366/99-09 on 990607-11 & 0823-27.One Violation Occurred Being Treated as NCV
ML20217G2631999-10-0707 October 1999
Informs That on 990930,NRC Staff Completed mid-cycle PPR of Hatch Plant & Did Not Identify Any Areas Where Performance Warranted More than Core Insp Program.Regional Initiative Insps to Observe Const Activities Will Be Conducted
ML20216G0251999-09-24024 September 1999
Concludes That All Requested Info of GL 98-01 & Supplement 1 Provided & Licensing Action for GL 98-01 & Supplement 1 Complete for Plant
ML20217B5271999-09-16016 September 1999
Forwards Insp Repts 50-321/99-05 & 50-366/99-05 on 990711-0821.No Violations Noted
ML20212A6411999-09-13013 September 1999
Forwards Safety Evaluation of Relief Request RR-V-16 for Third Ten Year Interval Inservice Testing Program
ML20211Q4801999-09-0101 September 1999
Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Copy of Slide Presentations & List of Questions Received from Participants Encl
ML20210T6421999-08-17017 August 1999
Discusses Licensee 950814 Initial Response to GL 92-01, Rev 1,Supp 1, Rv Structural Integrity (Rvid), Issued on 950519 to Plant.Staff Revised Info in Rvid & Being Released as Rvid Version 2
ML20210V3311999-08-13013 August 1999
Provides Synposis of NRC OI Report Re Alleged Untruthful Statements Made to NRC Re Release of Contaminated Matl to Onsite Landfill.Oi Unable to Conclude That Untruthful state- Ments Were Provided to NRC
ML20210Q4821999-08-0505 August 1999
Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr,As Listed,Identifying Individual to Take Exam,Thirty Days Before Exam Date
ML20210L7581999-08-0404 August 1999
Forwards Insp Repts 50-321/99-04 & 50-366/99-04 on 990530-0710.One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy
ML20210J9021999-08-0202 August 1999
Forwards SER Finding Licensee Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Edwin I Hatch Nuclear Plant,Units 1 & 2
ML20210J9501999-08-0202 August 1999
Forwards SER Finding Licensee Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Edwin I Hatch Nuclear Plant,Units 1 & 2
ML20210E1601999-07-20020 July 1999
Forwards Insp Repts 50-321/99-10 & 50-366/99-10 on 990616-25.One Violation Noted Being Treated as Ncv.Team Identified Lack of Procedural Guidance for Identification & Trending of Repetitive Instrument Drift & Calibr Problems
ML20209E4801999-06-30030 June 1999
Confirms 990630 Telcon Between M Crosby & DC Payne Re Arrangements Made for Administration of Licensing Exam at Plant During Weeks of 991018-1101
ML20196H8811999-06-25025 June 1999
Forwards Insp Repts 50-321/99-03 & 50-366/99-03 on 990418- 0529.No Violations Occurred.Conduct of Activities at Plant Generally Characterized by safety-conscious Operations & Sound Engineering & Maint Practices
ML20212J0541999-06-17017 June 1999
Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First
ML20207E7561999-06-0303 June 1999
Informs of Completion of Review & Evaluation of Info Provided by Southern Nuclear Operating Co by Ltr Dtd 980608, Proposing Changes to Third 10-Yr Interval ISI Program Plan Requests for Relief RR-4 & R-6.Requests Acceptable
ML20206Q0751999-05-0606 May 1999
Forwards Insp Repts 50-321/99-02 & 50-366/99-02 on 990307-0417.No Violations Noted
ML20206G1611999-05-0404 May 1999
Forwards SER Approving Util 990316 Revised Relief Request RR-P-14,for Inservice Testing Program for Pumps & Valves Pursuant to 10CFR50.55a(a)(3)(ii)
ML20206P6921999-04-27027 April 1999
Discusses 990422 Public Meeting at Hatch Facility Re Results of Periodic Plant Performance Review for Hatch Nuclear Facility for Period of Feb 1997 to Jan 1999.List of Attendees & Copy of Handouts Used by Hatch,Encl
ML20205T1831999-04-0909 April 1999
Informs That on 990316,S Grantham & Ho Christensen Confirmed Initial Operator Licensing Exam Schedule for Ei Hatch NPP for FY00.Initial Exam Dates Are 991001 & 2201 for Approx 12 Candidates.Chief Examiner Will Be C Payne
ML20205M3181999-04-0707 April 1999
Confirms Telcon Between D Crowe & Ph Skinner Re Mgt Meeting Scheduled for 990422 in Conference Room of Maint Training Bldg.Purpose of Meeting to Discuss Results of Periodic PPR for Plant for Period of Feb 1997 - Jan 1999
ML20205M3011999-04-0202 April 1999
Forwards Insp Repts 50-321/99-01 & 50-366/99-01 on 990124-0306.Non-cited Violation Identified
ML20205D3211999-03-24024 March 1999
Informs That Safety Sys Engineering Insp Previously Scheduled for 990405-09 & 19-23,rescheduled for 990607-11 & 21-25
ML20205A2991999-03-19019 March 1999
Advises of NRC Planned Insp Effort Resulting from Hatch PPR on 990202.PPR Involved Participation of All Technical Divs in Evaluating Insp Results & Safety Performance Info for Period of Feb 1997 - Jan 1999.Insp Plan for Future Encl
ML20207M1771999-03-11011 March 1999
Forwards SE Accepting Relief Request for Authorization of Alternative Reactor Pressure Vessel Exam for Circumferential Welds
ML20204E6601999-03-11011 March 1999
Discusses Ofc of Investigation Rept 2-1998-024 Re Contract Worker Terminated by General Technical Svc Supervisor for Engaging in Protected Activity.Evidence Did Not Substantiate Allegation & No Further Action Planned
ML20207D3131999-02-24024 February 1999
Forwards Insp Repts 50-321/98-09 & 50-366/98-09 on 981213- 990123.No Violations Noted.Conduct of Activities at Hatch Facility Generally Characterized by safety-conscious Operation,Sound Engineering & Maintenance
ML20203G4161999-02-17017 February 1999
Discusses Completion of Licensing Action for Bulletin 96-003, Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Bwrs
ML20203G3481999-02-0505 February 1999
Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 990407. Representative of Facility Must Submit Either Ltr Indicating No Candidates or Ltr Listing Names of Candidates for Exam
ML20199H8941999-01-21021 January 1999
Discusses Responses to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Controls, for Plant,Units 1 & 2
ML20199H8761999-01-21021 January 1999
Informs That Proposed GL 88-01 Examinations of Spring 1999 Refueling Outage of Plant,Unit 1 Acceptable
ML20199K1381999-01-12012 January 1999
Informs That on 990117,Region II Implemented Staff Reorganization as Part of agency-wide Streamlining Effort, Due to Staffing Reductions in FY99 Budget.Organization Charts Encl
ML20199F1331998-12-29029 December 1998
Forwards Insp Repts 50-321/98-07 & 50-366/98-07 on 981101- 1212.No Violations Identified.Activities at Hatch Facility Generally Characterized by safety-conscious Operations, Sound Engineering & Maintenance Practices
ML20199E7411998-12-23023 December 1998
Refers to 981105 Training Managers Conference Conducted at RB Russell Bldg with Representatives from All Utils.Agenda Used for Conference & List of Attendees Encl.Goal of Providing Open Forum of Operator Licensing Issues Was Met
ML20196J4771998-12-0707 December 1998
Refers to 980311 Submittal of Four New Relief Requests & One Revised Relief Request for IST Program for Pumps & Valves Ei Hatch Npp.Se Accepting Proposed Alternatives Encl
ML20196J2581998-12-0101 December 1998
Confirms Arrangements Made Between J Bailey & B Holbrook, Re Info Meeting Scheduled for 990210 to Discuss Licensee Performance,New Initiatives & Other Regulatory Issues Pertaining to Listed Facilities
ML20196J2851998-12-0101 December 1998
Advises of Planned Insp Effort Resulting from 981102 Insp Planning Meeting.Details of Insp Plan for Next 4 Months & Historial Listing of Plant Issues Called Plant Issues Matrix, Encl
ML20196F1661998-11-24024 November 1998
Forwards Insp Repts 50-321/98-06 & 50-366/98-06 on 980920-1031.Insp Rept Identifes Activities That Violate NRC Requirements But Not Subject to Enforcement Actions
ML20195D7961998-11-16016 November 1998
Informs That Licensee 980114 Request for Exemption from Requirements of General Design Criterion 56 for Edwin I Hatch Nuclear Plant,Unit 2 Found Acceptable & No Exemption from GDC-56 Required
ML20196C8001998-11-12012 November 1998
Forwards Copy of Forms a & B,Individual Answer Sheets & Exam Results Summary of GFE Section of Written Operator Licensing Exam,Administered on 981007 by Nrc.Without Encl
ML20195B7891998-11-0909 November 1998
Discusses Completion of Licensing Action for GL 97-04, Assurance of Sufficient Net Positive Suction Head for ECC & Containment Hrps, for Plant,Unit 1
ML20155H4181998-11-0303 November 1998
Advises That Info Contained in 980918 Application & 980813 Affidavit, GE14 Lua Fuel Bundle Description Rept, Will Be Withheld from Public Disclosure,Per 10CFR2.790
ML20155B6061998-10-28028 October 1998
Forwards Safety Evaluation of TR SNCH-9501, BWR Steady State & Transient Analysis Methods Benchmarking Tp
ML20155A5461998-10-21021 October 1998
Forwards FEMA Final Rept on Exercise of Offsite Radiological Emergency Response Plans for Hatch Plant,Conducted on 980520.No Deficiencies or Areas Requiring Corrective Actions Identified During Exercise
ML20155B2461998-10-15015 October 1998
Forwards Insp Repts 50-321/98-05 & 50-366/98-05.No Violations Noted
ML20155A6261998-10-15015 October 1998
Informs That NRC Recently Obtained Info Re Industrial Safety Issues at Hatch Facility.Info Indicated That Personnel Unnecessarily Working on Energized Electrical Equipment Without Appropriate Clothing
ML20154L4491998-10-14014 October 1998
Informs That NRC Reconsidered Relocation of PCP to PCP Manual Against Guidance in Regulatory Guide 1.143 & Believe That Locating of PCP in PCP Manual,Acceptable
ML20155B0371998-10-0909 October 1998
Extends Invitation to Attend Training Manager Conference to Be Held in Atlanta,Ga on 981105.Conference Designed to Inform Regional Training & Operations Mgt of Issues & Policies That Affect Licensing of Reactor Plant Operators
1999-09-24
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Inspection Report - Hatch - 1986021 |
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Georgia Power Company ATTN: Mr. J. H. Miller, J President P. O. Box 4545 Atlanta, GA 30302 Gentlemen:
SUBJECT: DOCKET N05. 50-321 AND 50-366, CONFIRMATORY MEASUREMENT RESULTS SUPPLEMENT TO INSPECTION REPORT NOS. 50-321/86-21 AND 50-366/86-21 As part of the NRC Confirmatory Measurements Program, spiked liquid samples were sent on September 22, 1986, to your facility for selected radiochemical analyse We are in receipt of your analytical results transmitted to us by your letter dated November 24, 1986, and the following comparison of your results to the known values are presented in Enclosure 1 for your information. The acceptance criteria for the comparisons are listed in Enclosure In our review of these data all comparative results were in agreement. These data should be reviewed in greater detail by cognizant staff members for any significant trends in the data among successive years in which samples have been analyzed by your facility. Any biases noted may be indicative of a programmatic weakness and your efforts sh.:uld be expended in determining reasons for such biase These results and any results from previous years pertaining to these analyses will be discussed at future NRC inspection
Sincerely, Virgil L. Brownlee, Chief Reactor Projects Branch 3 Division of Reactor Projects Enclosures:
1. Confirmatory Measurement Comparisons Criteria for Comparing Analytical Measurements cc w/encls: (See page 2)
8702090371 e70106 PDR ADOCK 05000321 Q PDR v y
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Alabama Power Company 2 cc w/ enc 1:
J. P. O'Reilly, Senior Vice President Nuclear Operations J. T. Beckham, Vice President, Plant Hatch H. C. Nix, Site Operations General Manager A. Fraser, Acting Site QA Supervisor L. Gucwa, Manager, Nuclear Safety and Licensing B. C. Arnold, Chemistry Supervisor bcc w/ enc 1:
NRC Resident Inspector Hugh S. Jordan, Executive Secretary Document Control Desk State of Georgia RII RII RII RII SAdamovitz JKahle DCollins e Algnatonis 12/ /86 12/ /86 12/ /86 12/ /86
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. JAN 0 A 1987 Gy rgia Power Company MITN: Mr. J. H. Miller, J President P. O. Box 4545 Atlanta, GA 30302 Gentlemen: y SUBJECT: DOCKET NOS. 50-348 AND 50-364, CONFIRMATORY MEASUREMENT RESULTS SUPPLEMENT TO INSPECTION REPORT NOS. 50-321/86-21 AND 50-366/86-21 As part of the NRC Confirmatory Measurements Program, spiked liquid samples were sent on September 22, 1986, to your facility for selected radiochemical analyse We are in receipt of your analytical results transmitted to us by your letter dated November 24, 1986, and the following comparison of your results to the known values are presented in Enclosure 1 for your informatio The acceptance criteria for the comparisons are listed in Enclosure In our review of these data all comparative results were in agreement. These data should be reviewed in greater detail by cognizant staff members for any significant trends in the data among successive years in which samples have been analyzed by your facility. Any biases noted may be indicative of a programmatic weakness and your efforts should be expended in determining reasons for such biase These results and any results from previous years pertaining to these analyses will be discussed at future NRC inspection '
Sincerely, Virgil L. Brownlee, Chief Reactor Projects Branch 3 Division of Reactor Projects Enclosures:
- Confirmatory Measurement Comparisons Criteria for Comparing Analytical Measurements cc w/encls: (Seepage 2)
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Alabama Power Company 2 cg w/ encl:
t(. P. O'Reilly, Senior Vice President uclear Operations T. Beckham, Vice President, Plant H&tch
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. C. Nix, Site Operations General
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%. Fraser, Acting Site QA Supervisor W. Gucwa, Manager, Nuclear Safety lI.andLicensing C. Arnold, Chemistry Supervisor bec w/ encl:
MCResidentInspector t%gh S. Jordan, Executive Secretary Document Control Desk State of Georgia r
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ENCLOSUftE 1 -)
CONFIRMATORY MEASUREMENT COMPARIS006S OF FE-55 ANALYSIS FOR HATCH NUCLEAR PLANT ON SEPTEM8ER 22, 1986
. MRC Ratio Licensee (Licensee /NRC) yp_a ri son C
Samste ID fuCi/onit) ' fuCi/ unit) Resolution 52 0.92 Agreement H-3 2. f4 E-5 2.60 i .05 E-5 48 1.19 Agreement Fc-55 2.3 E-5 1.93 i .084 E-5
.76 Ag reement Sr-89 2.5 E-5 3.27 i .10 E-5 33 26 1.07 Agreement S r-90 3.3 E-6 3.09 i .12 E-6
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- ,y ENCLOSURE Criteria for Comparing Analytical Measurements This enclosure provides criteria for comparing results of capability tests and verif' cation measurements. The criteria are based on an empirical relationship which combines prior experience and the accuracy needs of this progra In these criteria, the judgement limits denoting agreement or disagreement between licensee and NRC results are variable. This variability is a function of the NRC's value relative to its associated uncertainty, referred to in this program as " Resolution"2 increases, the range of acceptable differences between .
the NRC and licensee values should be more restrictive. Conversely, poorer agreement between NRC and licensee values must be considered acceptable as the resolution decrease For comparison purposes, a ratio r of the licensee value to the NRC value for each individual nuclide is computed. This ratio is then evaluated for agreement based on the calculated resolution. The corresponding resolution and calculated ratios which denote agreement are listed in Table .1 below. Values outside of the agreement ratios for a selected nuclide are considered in disagreemen " Resolution = NRC Reference Value for a Particular Nuclide '
Associated Uncertainty for the Value
' Comparison Ratio = Licensee Value NRC Reference Value Confirmatory Measurements Acceptance Criteria Resolutions vs. Comparison Ratio Comparison Ratio
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for Resolution Agreement
<4 0.4 - .5 - .6 - 1.66 16 - 50 0.75 - 1.33 51 - 200 0.80 - 1.25
>200 0.85 - 1.18
