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| {{Adams | | {{Adams |
| | number = ML20138L983 | | | number = ML20199F357 |
| | issue date = 12/12/1985 | | | issue date = 03/20/1986 |
| | title = Safety Insp Repts 50-317/85-31 & 50-318/85-26 on 851118-22. No Violation Noted.Major Areas Inspected:Radiation Protection Program During Outage,Including External Dosimetry Training | | | title = Ack Receipt of 860113 Ltr Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-317/85-31 & 50-318/85-26 & of Plans Re Resolution of Open Items Concerning Control Room Habitability |
| | author name = Clemons P, Shanbaky M | | | author name = Martin T |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| | addressee name = | | | addressee name = Tiernan J |
| | addressee affiliation = | | | addressee affiliation = BALTIMORE GAS & ELECTRIC CO. |
| | docket = 05000317, 05000318 | | | docket = 05000317, 05000318 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = 50-317-85-31, 50-318-85-26, NUDOCS 8512200158 | | | document report number = NUDOCS 8603280171 |
| | package number = ML20138L974
| | | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE |
| | document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS | | | page count = 2 |
| | page count = 7 | |
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| V U.S. NUCLEAR REGULATORY COMMISSION
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| ==REGION I==
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| Report No /85-31 50-318/85-26 Docket No License Nos. OPR-53 Priority --
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| Category C DPR-69 Licensee: Baltimore Gas and Electric Company P. O. Box 1475 Baltimore, Maryland 21203 Facility Name: Calvert Cliffs Nuclear Power Plant, Units 1 and 2 Inspection At: Lusby, Maryland Inspection Conducted: November 18-22, 1985 Inspector: /2//$bT P. Clemons, Radiation Specialist ' date Approved by: kL dM b t t(itj h5 M. Shanbaky, Chief / date PWR Radiation Safety Section Inspection Summary: Inspection on November 18-22, 1985 (Report Nos. 50-317/
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| 85-31 and 50-318/85-26).
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| Areas Inspected: Routine, unannounced safety inspection of the Radiation Pro-tection Program during the outage including: external dosimetry training, respiratory protection, exposure control, surveys, procedures, posting and labeling, and outstanding items. The inspection involved 31 hours onsite by one regionally based inspecto Results: No violations were identified during the course of this inspectio PDR ADOCK 050 g 7
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| | MAR 2 01986 Docket Nos. 50-317 License Nos. DPR-53 50-318 DPR-69 Baltimore Gas and Electric Company ATTN: Mr. J. A. Tiernan Vice President Nuclear Energy P. O. Box 1475 Baltimore, Maryland 21203 Gentlemen: |
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| | Subject: Combined inspection 50-317/85-31 and 50-318/85-26 |
| | ! This refers to your letter dated January 13, 1986, in response to our letter dated December 13, 198 Thank you for informing us of your plans regarding the resolution of open items related to control room habitabilit Your cooperation with us is appreciate |
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| | Sincerely, OS31sn1 SI-- :c 9f: |
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| | o s art n, Directo Division of Radiation Sa y and Safeguards CC: |
| | M. Bowman, General Supervisor, Technical Services Engineering : |
| | Thomas Magette, Administrator, Nuclear Evaluations l Public Document Room (PDR) l Local Public Document Room (LPOR) l Nuclear Safety Information Center (NSIC) i NRC Resident Inspector ! |
| | State of Maryland (2) l l |
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| DETAILS 1.0 Persons Contacted 1.1 Licensee Personnel N. Millis, General Supervisor - Radiation Safety J. Carlson, Assistant General Supervisor - Radiation Safety P. Rizzo, Supervisor - Technical Training L. Smialek, Senior Plant Health Physicist W. Putman, Senior Quality Assurance Auditor E. Roach, Quality Assurance Specialist 1.2 NRC Personnel
| | R603280171 860320 I PDR ADOCK 05000317 O PDR OFFICIAL RECORD COPY RL CC 85-31/26 - 0001. /12/86 s l l |
| ~ Foley, Senior Resident Inspector D. Trimble, Resident Inspector Other licensee personnel were contacted and interviewed during the inspectio .0 Purpose The purpose of this routine safety inspection was to review the perfor-mance of the licensee's radiation protection program during the 1985 refueling outage with respect to the following elements:
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| * external dosimetry program;
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| * training of outage personnel; -
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| a respiratory protection program; e exposure control;
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| * surveys; _
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| * procedures; and
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| * posting and labelin , | |
| 3.0 Licensee Action on Previous Findings (Closed) Violation (317/85-20-01 and 318/84-20-01) Failed to adhere to the criteria of Appendix B, Part 50. The inspector reviewed the corrective action specified in the licensee's response dated October 26, 1984. The corrective action appeared to be adequat .0 External Dosimetry Program The licensee's external dosimetry program was reviewed with respect to the criteria contained in 10 CFR 20, " Standards For Protection Against Radiation." i
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| | J Baltimore Gas and Electric' |
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| | Region I Docket Room (with concurrences). |
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| The licensee's implementation of the external dosimetry program was evaluated by the following methods:
| | ! DRP Section Chief M. McBride, RI, Pilgrim T. Kenny, SRI, Salem D..Jaffe, LPM, NRR |
| * Interviews of the Dosimetry Supervisor and staff;
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| * Review of dosimetry records of selected personne Within the scope of this review, no violations were identifie The following was noted:
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| * The external dosimetry program was adequate and effectiv * The licensee's dosimetry group was well staffe * The licensee's External Dosimetry Program is NVLAP certified. This certification demonstrates an acceptable level of minimum performance in evaluating personnel radiation exposure .0 Surveys The licensee's survey program was reviewed against criteria contained in ,
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| 10 CFR 20.201, " Surveys".
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| The licensee's performance relative to these criteria was determined by discussion with the Radiation Controis-Ops Supervisor and by reviewing appropriate radiological survey record The licensee's records indicate that the surveys taken throughout the Controlled Area are adequat Within the scope of this review, no violations were identifie .0 Posting and Labeling
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| The licensee's program for area posting and control was reviewed against the criteria in 10 CFR 20.203, " Caution signs, labels, signals and Controls".
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| The licensee's performance relative to these criteria was determined from a tour of the Controlled Areas and from discussions with the staff members.
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| | .RI:DRSS Dragoun/mm Shan Bellam /8/86 34 % /86 3//7 /86 . 0FFICIAL RECORD RL CC 85-31/26 COPY- 0002, /12/86 |
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| Throughout all of the areas inspected, posting and labeling were more than adequat Within the scope of this review, no violations were identified.
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| 7.0 Respiratory Protection Program The Itcensee's respiratory protection program was reviewed with respect to the criteria contained in 10 CFR 20.103, " Exposure of individuals to concentrations of radioactive materials in air in restricted areas".
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| The implementation of the licensee's respiratory protection program during the outage was evaluated by:
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| * interviews of the personnel responsible for various aspects of the program;
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| * reviewing records that indicated that breathing air had been sampled and analyzed to assure Grade D qualit Procedures for implementing the respiratory protection program appeared
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| .to be adequat Within the scope of this review, no violations 'iere identifie .0 Procedures The adequacy and effectiveness of the licensee's procedures were reviewed against the criteria contained in Technical Specification 6.8, "Proce-dures", and Technical Specification 6.11, " Radiation Protection Program".
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| Procedures reviewed included:
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| * RSP 1-117, " Selection, Issuance And Wearing Of Respiratory Protection Devices Used At Calvert Cliffs Nuclear Power Plant",
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| * RSP 2-306, " Operation And Maintenance Of The. Containment And Plant Breathing Systems",
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| * RSP 2-301, " Respiratory Protection Device Maintenance",
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| * RSP 3-201, " Personnel Dosimetry",
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| * RSP 3-202, "Special Dosimetry".
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| Within the scope of this review, no violations were identifie ' Training The licensee's training program was reviewed against criteria contained in 10 CFR 19.12, " Instructions to Workers" and ANSI N18.1, 1971, " Selection and Training of Nuclear Power Plant Personnel".
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| The licensee's performance relative to these criteria was determined by discussion with a Training Instructor, and by review of documentatio The lesson plans used in providing training for the Contractor Health Physics Technicians appeared to be more than adequat Within the scope of this review, no violations were identifie .0 Exposure Control The licensee's external exposure control program was reviewed against cri-teria contained in 10 CFR 20.202, " Personnel monitoring". The licensee's program for controlling personnel exposure and maintaining exposure ALARA during the 1985 Refueling Outage was evaluated by:
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| * Interviews of the ALARA and Radiation Control Supervisors and selected members of their staff;
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| * Review of procedure RSP-106, "Special Work Permit"; and
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| Review of activities and documentation associated with nozzle dam installation and remova ,
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| Within the scope of this review, the following was identified:
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| * The inspector determined that 15-20 licensee employees participated in the nozzle dam operations during this outage. The licensee's exposure records indicated that this job was accomplished with the expenditure of 9.9 man-rem. This represents a significant reduction in exposure in performing this job. According to the Radiation Control - ALARA Supervisor, the lowest exposure received in doing this job, prior to this outage, was 47 man-re The licensee is to.be commended for the tremendous effort that resulted in this significant reduction in exposur Within the scope of this review, no violations were identifie .0 Control Room Habitability Combined Inspection Report Nos. 50-317/85-27 and 50-318/85-25 provided the results of a review of Control Room Habitability at the Calvert Cliffs Nuclear Station, Units 1 and Since the issuance of this inspection report, additional findings relative to the acceptability of Control Room Habitability at Calvert Cliffs have been identified by the NRR Review Group. These additional findings are stated below along with NRC requested actio , _ .
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| Additional Findings-(a) Leakage was measured (1000-2000 cfm) through the isolation dampers with the system in the recirculation mode and flow (10-25% of rated flow) was measured through the charcoal absorber unit when it was
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| isolated. (317/85-31-01)
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| The licensee should provide the following:
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| the results'of the current evaluation to establish total inleakage rate for the Control Room envelope, and a
| | BALTIMORE g GAS AND ELECTRIC CHARLES CENTER P. O. BOX 1475 * BALTIMORE, MARYLAND 21203 JOSEPH A.TIERNAN Vect PatstDENT NucLEAn ENERGY January 13, 1986 U. S. Nuclear Regulatory Commission ~ Docket No Region I 50-318 631 Park Avenue License No DPR-53 King of Prussia, PA 19406 DPR-69 ATTENTION: Mr. Thomas T. Martin, Director Division of Radiation Safety & Safeguards Gentlemen: |
| the date as to when the identified deficiencies will be correcte (b) Missing screws and bolts were evident and, as a consequence, ducting seam leakage was note Additionally, several holes were found at stress points on the fabric expansion joint It was stated that inspection and repair of this system was needed to minimize inleak-age during an accident. (317/85-27-01 and 318/85-25-01)
| | This refers to Inspection Report 50-317/85-31, 50-318/85-26; which identified apparent deficiencies in the area of Control Room Habitability. We have conducted a thorough review of the findings and have worked with Mr. P. Clemons of your office previously in this are Enclosure (1) to this letter is a written statement in reply to those findings noted in your lette Based on the information provided in Enclosure (1), we request you reevaluate the appropriate findings. Should you have further questions regarding this reply, we will be pleased to discuss them with yo Very truly yours, 3AT/SRC/gla Enclosure cc: D. A. Brune, Esquire G. F. Trowbridge, Esquire D. H. Jaffe, NRC T. Foley, NRC ' |
| The licensee should provide the following:
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| * status of maintenance deficiencies that have been corrected,
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| * results of the evaluation of the walkdown of effected duct work, and
| | - Obuju%a (vavu l q Q . |
| * the date when all activities including identified deficiencies will be correcte (c) Technical Specification 4.7.6.1.e.2 requires both isolation valves of each outside air intake to close on a control room high radiation test signal. At Calvert Cliffs, only the butterfly damper on each intake closes on high radiation signal. (317/85-31-02)
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| The licensee should provide the following:
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| * corrective actions to be taken, and a
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| the date when the deficiencies will be correcte .0 Exit Interview The inspector met with the personnel denoted in Section 1 at the conclu-sion of the inspection on November 22, 1985. The scope and findings of-the inspection were discussed at that tim The licensee was given a copy of the NRR findings of the Control Room Habitability Study that was performed in September, 1985. A copy of the material provided to the licensee is attached to this inspection repor No other written material was provided to the license . - _ - -
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| Attachment to Combined Inspection Report 50-317/85-31; 50-318/85-26 Control Room Habitability Findings
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| Leakage was measured (1000-2000 cfm) through the isolation dampers with the system in the recirculation mod *
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| Flow (10-25% of rated flow) was measured through the charcoal absorber unit when it was isolate * The licensee representative knowledgeable about the control room HVAC system was from BG&E headquarters. His understanding of the system and its mode of operation differed from the manner in which the system operate *
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| Missing screws and bolts were evident and, as a consequence, ducting seam leakage was noted. Additionally, several holes were found at stress points on the fabric expansion joint * Technical Specification 4.7.6.1.e.2 requires both_ isolation valves of each outside air intake to close on a control room high radiation test signal. At Calvert Cliffs, only the butterfly damper on each intake closes on high radiation signa * The location where equipment temperature was monitored to show conformance with Technical Specification 4.7.6.1.a was not near such equipment but on a control room wal *
| | t ENCLOSURE (1) |
| The manner in which the control room HVAC system is operated and its configuration is quite different from that which would be concluded from Calvert Cliffs III.D.3.4 submitta * Laboratory testing of charcoal should be at 30 C rather than 130 C consistent with ASTM D3803-1979 and the allowable penetration for this test should be 1% in accordance with Table 2 of Regulatory Guide 1.5 *- The cooling load for the control room is 116.5 tons. The capacity-of the safety grade system is 96 tons. After a series of cooling problems in 1980 a new non-safety grade system was added to handle control room cooling during normal operation. The adequacy of the revised HVAC system has not been analyze * The 19 cfm of inleakeage used by the licensee in the III.D. analysis has never been verifie *
| | REPLY TO APPENDII A OF IEtC INSPECTION REPORT 50-317/8 5L31; S0-318/85-26 FINDING 317/8 5L31-01 We plan to measure the isolation damper and access door leakage rates, in addition to estimating the leakage rate in the duct |
| The leak rate assumed in the III.D.3.4 evaluation was based upon factory test data and anticipated performance of the butterfly and louvered damper The actual performance of the dampers shows substantially greater leakag .
| | . work outside the Control Room envelope . A total inleakage rate l will then be estimated and, if necessary, used in a new dose calculation for Control Room Operator We will provide the i results of the inleakage determination and dose calculation by l February 1,198 We will determine any appropriate corrective action, if |
| | ; necessary, when deficiencies are note FINDING 317/8 5L27-01; 318/8 542 5L01 l The following maintenance deficiencies have been corrected: |
| | oCracked panels in the air handling unit have been repaired (welded), |
| | oAir leaks at the cooling coil penetrations have been sealed, and oLatches on duct windows have been replace In addition to the missing screws and bolts, and holes at stress l points on the fabric expansion joints, the following deficiencies were noted during the walkdown of affected ductwork: |
| | oCrack in a panel for #12' Air Handling Unit, and oMissing plugs in test penetration holes in the |
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| | ductwor These deficiencies will be corrected by April 1, '198 ; FINDING 317/8 5631-02 Licensee Event Report 8 5-014 (Unit 1) documented specific issues ; |
| | in this findin The -louvered dampers were repaired and shut o ' |
| | a Control Room high radiation signa The following corrective actions were taken: |
| | oBroken blade brackets were replaced, oDamper linkages were adjusted, and oA sampling of similar dampers were inspecte We intend to evaluate the isolation capability of the louvered dampers by measuring the leakage through these dampers in the recirculation mode with the butterfly dampers open. This evaluation should be completed by April 1, 198 < |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20138H3831999-10-25025 October 1999
Forwards Draft Model of Renewed License for Calvert Cliffs, Unit 2 to Illustrate How List of Minimum Requirements Could Be Incorporated Into License Condition
ML20217M9991999-10-22022 October 1999
Forwards Response to NRC 990930 RAI Re Void Swelling Degradation Mechanism,Per License Renewal Application for Ccnpp,Units 1 & 2
ML20217M1721999-10-19019 October 1999
Forwards NRC Rept Number 17, Requal Tracking Rept Form Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates
ML20212M2631999-10-0404 October 1999
Informs That Staff Concluded That Licensee Responses to GL 97-06 Provides Reasonable Assurance That Condition of Util SG Internals in Compliance with Current Licensing Bases for Calvert Cliffs Nuclear Power Plant
ML20216J8671999-10-0101 October 1999
Forwards Rev 52 to QA Policy for Calvert Cliffs Nuclear Power Plant. Rev Accurately Presents Changes Made Since Previous Submittal,Necessary to Reflect Info & Analyses Submitted to NRC or Prepared,Per to NRC Requirements
ML20212J7811999-09-30030 September 1999
Requests That Licensee Address Potential Aging Mgt Issue Re Effects of Void Swelling of Rv Internals by Making Plant Specific Commitment to Implement Focused age-related Degradation Insp for Evidence of Void Swelling in Future
ML20212J5611999-09-29029 September 1999
Informs That on 990916,NRC Completed mid-cycle Plant Performance Review of Calvert Cliffs.No Areas in Which Util Performance Warranted Addl Insp Beyond Core Insp Program Identified.Historical Listing of Plant Issues,Encl
ML20216H7831999-09-28028 September 1999
Forwards Addl Info Re NRC SER for Ccnpp,Units 1 & 2,per License Renewal Application
ML20212D5361999-09-20020 September 1999
Forwards Rev 1 to Calculation CA04048, Fuel Handling Accident During Reconstitution, as Agreed During 990909 Telcon
ML20212C1861999-09-15015 September 1999
Requests That NRC Complete Review of TR CED-387-P,Rev 00-P, Abb Critical Heat Flux Correlations for PWR Fuel, by 000201.Util Expects to Use ABB-NV Correlation for Current non-mixing Vane Fuel in Reload Analyses in 2000 for Ccnpp
ML20212A2001999-09-0808 September 1999
Forwards Insp Repts 50-317/99-06 & 50-318/99-06.Two Violations Being Treated as Noncited Violations
ML20211N8971999-09-0707 September 1999
Responds to Ltr to D Rathbun of NRC Dtd 990720,in Which Recipient Refers to Ltr from Wc Batton Expressing Support on Renewal Application of Baltimore Gas & Electric Co for Calvert Cliffs Plants
ML20211H9841999-08-31031 August 1999
Provides Comments Re Data Entered in Rvid for Ccnpp,Units 1 2,per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity
ML20211K3091999-08-27027 August 1999
Informs That During 990826 Telcon,L Briggs & B Bernie Made Arrangements for NRC to Inspect Licensed Operator Requalification Program at Calvert Cliffs Npp.Insp Planned for Wk of 991025
ML20211J1611999-08-17017 August 1999
Documents Bg&E Consultations with MD Dept of Natural Resources Re Potential Impacts to Chesapeake Bay Critical Area & Forest Interior Dwelling Bird Habitat,Per Ccnpp License Renewal.Telcons Ref Satisfy Consulting Requirement
ML20210V1181999-08-17017 August 1999
Forwards Toxic Gases Calculations for Control Room Habitability,As Discussed During 990713 Telcon.Util Will Make Final Submittal for Toxic Gases After NRC Has Completed Review of ARCON96
ML20210T5061999-08-16016 August 1999
Forwards Rev 0 to Ccnpp COLR for Unit 2,Cycle 13, Per Plant TS 5.6.5
ML20210U2761999-08-13013 August 1999
Forwards Listed Info Re Guarantee of Payment of Deferred Premiums for Ccnpp,Units 1 & 2,IAW 10CFR140.21 Requirements
ML20210S8131999-08-12012 August 1999
Forwards Summary of Various Open Licensing Actions for Bg&E That Were Completed During Unit 2 Refueling Outage Ending 990506
ML20210S8101999-08-12012 August 1999
Forwards Application Requesting Renewal of License for Mv Seckens,License SOP-10369-2.Without Encl
ML20210S7901999-08-12012 August 1999
Forwards semi-annual Fitness for Duty Program Performance Data for Period of 990101-990630,IAW 10CFR36.71(d)
ML20210Q1941999-08-11011 August 1999
Informs That Info Submitted in 981130 Application Re CEN-633-P,Rev 03-P,dtd Oct 1998,marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended
ML20210N5881999-08-0606 August 1999
Forwards ISI Rept for Ccnpp,Unit 2,fulfilling Intentions & Requirements Stated in Program Plan & Commitment to Comply with ASME Code Section XI ISI Requirements
ML20210N1291999-08-0505 August 1999
Forwards NRC Response to W Batton Ltr Expressing Support of Renewal Application for Calvert Cliffs Plants as Requested in Ltr
ML20210N5491999-08-0505 August 1999
Requests That License SOP-10371-2,for RW Scott,Be Renewed IAW 10CFR55.57.Individual Has Satisfactorily Discharged License Responsibilities Competently & Safely.Without Application
ML20210N5471999-08-0505 August 1999
Requests That License SOP-10031-3,for DF Theders,Be Removed from Active Files for Ccnpp,Due to Individual Being Reassigned to Position No Longer Requiring License
ML20210N9291999-08-0404 August 1999
Forwards Clarification to Initial Response to Biennial Rept on Status of Decommissioning Funding,As Required by 10CFR50.75(f)(1)
ML20210J0741999-07-30030 July 1999
Expresses Appreciation for Participation in Y2K Training & Tabletop Exercise on 990714.Suggests Referral to NRC Y2K Web Site to View Issues & Lessons from Tabletop That Will Be Tracked by Nrc.Web Site Should Reflect Info within 2 Wks
ML20211B5381999-07-30030 July 1999
Expresses Appreciation for Support in Y2K Training & Tabletop Exercise Held on 990714.Suggests Referral to NRC Y2K Web Site to View Issues & Lessons from Tabletop That Will Be Tracked by NRC
ML20211C0951999-07-30030 July 1999
Expresses Appreciation for Participation in Y2K Training & Tabletop Exercise Held on 990714
ML20211C3251999-07-30030 July 1999
Expresses Appreciation for Participation in Y2K Training & Tabletop Exercise Held on 990714
ML20210E4941999-07-23023 July 1999
Informs That 1999 Emergency Response Plan Exercise Objectives Is Scheduled for Wk of 991025.Exercise Scenario Will Test Integrated Capability & Major Portion of Elements Existing within Emergency Response Plan
ML20210D0911999-07-22022 July 1999
Responds to to Chairman Jackson Referring to Ltr from New 7th Democratic Civic Club,Inc.Forwards Staff Response to W Batton,President of New 7th Democratic Civic Club,Inc
ML20210C5011999-07-21021 July 1999
Informs That SL Walters,License OP-10096-3 & CC Zapp,License Number SOP-2188-9,have Been Reassigned within Organization & No Longer Require NRC License,Per 10CFR50.74(a).Removal of Subject Licenses from Active Files for Ccnpp,Requested
ML20210C2681999-07-20020 July 1999
Forwards Certified Copy of Listed Nuclear Liability Policy Endorsement,Per 10CFR140.15(e)
ML20210A5021999-07-20020 July 1999
Responds to ,Expressing Support for Renewal of Operating Licenses for Calvert Cliffs Plant & to Concerns Re Lack of Specificity for License Renewal Regulations & Length of Time Set Aside for Public Comment
ML20211N9101999-07-20020 July 1999
Forwards Correspondence Author Received from New 7th Democratic Club Civic,Inc Raising Some Serious Concerns About Renewal of Nuclear Reactor Licenses for Calvert Cliffs Power Plant
ML20210C8461999-07-19019 July 1999
Informs That CF Farrow,License OP-10648-1,will No Longer Be Employed with Bg&E,As of 990709,per 10CFR50.74(a).Removal of Subject License from Active Files for Ccnpp,Requested
ML20209J5171999-07-16016 July 1999
Forwards Comments from Accuracy Review of License Renewal Application SER
ML20210B7651999-07-15015 July 1999
Forwards SER Denying Licensee Proposed TS Amend Dtd 981120, to Delete TS Requirements for Tendon Surveillance & Reporting Because TS Requirements Duplication of Requirements in 10CFR50.55a.Notice of Denial Encl
ML20209G2081999-07-13013 July 1999
Forwards Insp Repts 50-317/99-05 & 50-318/99-05 on 990509- 0626.No Violations Noted
ML20210A6311999-07-0606 July 1999
Discusses Closure of TACs MA0532 & MA0533 Re Response to Requests for Addl Info to GL 92-01,rev1,suppl 1, Reactor Vessel Structural Integrity, for Plant,Units 1 & 2
ML20209C1391999-07-0202 July 1999
Forwards Responses to Open & Confirmatory Items Based on Review of SER for Bg&E Application for Renewal of Operating Licenses for Calvert Cliffs.Bg&E Intends to Forward Comments Based on Accuracy Verification in Near Future
ML20210D1531999-06-30030 June 1999
Informs of Receipt of from New 7th Democratic Civic Club,Inc Expressing Support for License Renewal. Requests Consideration in Addressing Concerns & Recommendations
ML20209B5781999-06-29029 June 1999
Submits Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. GL 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl
ML20210D1741999-06-24024 June 1999
Expresses Opinions on Renewal of Nuclear Reactor Licenses Re Plant & Support Renewal Application of Bg&E.Requests That NRC Revise Procedures to Allow Sufficient Time for Public to Review,Evaluate & Respond to Info
ML20211H8431999-06-23023 June 1999
Ack Participation of Calvert Cliffs Nuclear Engineering Dept in NRC Cooperative Research Project with Univ of Virginia. Copy of Relevant Portion of NRC Cooperative Agreement with Univ of Virginia Encl
ML20196C6831999-06-21021 June 1999
Discusses Proposed Alternative Submitted by Bg&E for Calvert Cliffs NPP to Requirements of 10CFR50.55a(g)(4) in Regard to Compliance with Latest Approved Edition of ASME Code,Section XI for Third Ten Year Insp Interval Beginning on 990701
ML20196C4291999-06-21021 June 1999
Forwards Rev to ERDS Data Point Library for Ccnpp,Unit 2,per 10CFR50,App E,Section VI.3.a.Table Provides Brief Summary of Changes
ML20195J8271999-06-16016 June 1999
Ack Receipt of to Jackson,Chairman of NRC Re Environ Impacts of Increased Patuxtent River Complex Flight Operations on Ccnpp.Clarification & Correction of Listed Statement Found on Page Two,Provided
1999-09-08
[Table view]
Category:NRC TO UTILITY
MONTHYEARML20062G6791990-11-21021 November 1990
Forwards SE Determining That Load Profile Used During Surveillance Test Procedures Meets Requirement of Tech Spec 4.8.2.3.2.e,per Unresolved Item Noted in Insp Repts 50-317/90-80 & 50-318/90-80
IR 05000317/19900281990-11-14014 November 1990
Discusses 901102 Enforcement Conference Re Insp Repts 50-317/90-28 & 50-318/90-28 Covering Security Event
ML20216K1541990-11-13013 November 1990
Forwards Safety Insp Repts 50-317/90-31 & 50-318/90-31 on 901029-1102.No Violations Noted
ML20217A0131990-11-0909 November 1990
Forwards Insp Repts 50-317/90-25 & 50-318/90-25 on 900916-1020.One Noncited Violation Noted
ML20058E9821990-11-0101 November 1990
Forwards List of Unimplemented Generic Safety Issues at Plant,Per Util 900627 Response to Generic Ltr 90-04
ML20058A7001990-10-19019 October 1990
Forwards Safeguards Insp Repts 50-317/90-28 & 50-318/90-28 on 901010 & 11.Violation Noted
ML20058A6841990-10-17017 October 1990
Forwards Insp Repts 50-317/90-23 & 50-318/90-23 on 900812- 0915.No Violations Noted
ML20059N9421990-10-12012 October 1990
Advises of Resolution of Auxiliary Feedwater Issue,Per .Issue Concerns Ability of AFW Sys to Provide Flow to Steam Generators Following Pipe Break
ML20062B2041990-10-12012 October 1990
Advises of Acceptance of 900924 Response to Generic Ltr 90-03, Relaxation of Staff Position in Generic Ltr 83-28, Item 2.2,Part 2 Vendor Interface for Safety-Related Components
IR 05000317/19900081990-10-11011 October 1990
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-317/90-08 & 50-318/90-08
ML20059N5781990-10-0909 October 1990
Advises That Util 900510 Submittal of Revised Section of Inservice Insp Program Plan Addressed Provisions of Safety Evaluation
ML20062B8361990-10-0909 October 1990
Forwards Special Team Insp Rept 50-317/90-24 on 900904-07 Re 900830 Reactor Vessel Water Level Anomaly
ML20059N2231990-10-0101 October 1990
Forwards Safety Evaluation Accepting Proposed Actions Re Potential Design Deficiency,Per LER 89-023
ML20059N1181990-09-28028 September 1990
Forwards Safety Insp Repts 50-317/90-22 & 50-318/90-21 on 900827-31.No Violations Noted.Post Maint Testing Program Assessed to Be Comprehensive,Well Implemented & Met Objectives of Performance Improvement Program
ML20059M7751990-09-27027 September 1990
Advises That NRC Approved Request for Relief from ASME Code Section XI Re Reactor Coolant Charging Pumps in
ML20059K7041990-09-0707 September 1990
Ack Receipt of Util 900515 Response to Violations Noted in Insp Repts 50-317/90-01 & 50-318/90-01.Agrees That Thrust of Notice of Violation Not Accurate But That Actual Violation Was Failure to Comply w/10CFR50,App B,Criterion Xvi
ML20059E3371990-08-27027 August 1990
Forwards Insp Repts 50-317/90-17 & 50-318/90-15 on 900710-13.No Violations Noted.Util Requested to Provide Complete Corrective Actions Being Considered to Prevent Recurrence of Welding Deficiencies within 30 Days
ML20059E1921990-08-24024 August 1990
Forwards Insp Repts 50-317/90-18 & 50-318/90-17 on 900716-20.No Violations Noted
ML20059E2981990-08-23023 August 1990
Advises That 890313,1103 & 900228 Revs 9,10 & 11 to Plant Contingency Plan,Consistent w/10CFR50.54 & Acceptable.Revs Withheld (Ref 10CFR73.21)
ML20058N3641990-08-0909 August 1990
Forwards Notice of Withdrawal of 900801 Applications for Amend to License DPR-69 Re Shift of Min Pressurization Temp Between 530 & 20 Psia on Heatup & Cooldown Curves
ML20058P1331990-08-0808 August 1990
Forwards Radiation Safety Insp Repts 50-317/90-14 & 50-318/90-12 on 900625-29.No Violations Noted
ML20058N0481990-08-0606 August 1990
Discusses Licensee Engineering Initiatives.Other Power Reactor Licenses in Region 1 Should Provide for Sharing of Info & Experiences Involving Engineering Initiatives & Solutions of Problems Common to All
ML20056A4081990-07-24024 July 1990
Forwards Insp Repts 50-317/90-12 & 50-318/90-11 on 900604-08.No Violations Noted
ML20055G5931990-07-18018 July 1990
Forwards Corrected Cover Ltr for Insp Repts 50-317/90-10 & 50-318/90-10,revising Insp Rept Numbers
ML20055H1211990-07-18018 July 1990
Advises That Encl Review of Cen 387-P, C-E Owners Group Pressurizer Surge Line Flow Stratification Evaluation, Inadequate.Insufficient Bases Provided to Conclude That Power Surge Line Meets Code Limits for 40-yr Plant Life
ML20055G5951990-07-18018 July 1990
Corrected Cover Ltr Forwarding Insp Repts 50-317/90-10 & 50-318/90-10
ML20055F9241990-07-17017 July 1990
Informs That All Activities Re Reactor Vessel Level Monitoring Sys & Core Exit Thermocouples Completed Except for Tech Specs Based on Review of 870501 & 880427 Submittals
ML20055F9561990-07-17017 July 1990
Advises That Actions Re NRC Bulletin 87-002, Fastener Testing to Determine Conformance W/Applicable Matl Specs, Adequate,Per Insp Repts 50-317/90-08 & 50-318/90-08
ML20055G1331990-07-12012 July 1990
Forwards Insp Repts 50-317/90-13 & 50-318/90-13 on 900603-30.No Violations Observed
ML20055F5421990-07-10010 July 1990
Advises That Requalification Program Evaluation Scheduled for Wk of 901022.Facility Requested to Furnish Approved Items Listed in Encl 1, Ref Matl Requirements in Order for Examiners to Adequately Prepare for Visit
ML20055E5311990-07-0606 July 1990
Forwards Request for Addl Info Re Facility Control Assembly Action Program,Per 900607 Control Element Assembly Failure at Maine Yankee.Confirmation of NRC Understanding That Util Intends to Implement C-E Plan Also Requested
ML20055E9081990-07-0202 July 1990
Forwards Exam Repts 50-317/90-07OL & 50-318/90-07OL on 900507-10
ML20055J3181990-06-29029 June 1990
Forwards Insp Repts 50-317/90-10 & 50-318/90-10 on 900604-08.No Violations Noted
ML20055D0731990-06-27027 June 1990
Advises That Reactor Operator & Senior Reactor Operator Licensing Exams Scheduled for Wk of 901029.Ref Matls,Listed on Encl,Should Be Provided by 900829
IR 05000317/19900041990-06-14014 June 1990
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-317/90-04 & 50-318/90-04.Also Ack Schedular Slippage from 900601 to 0701 for Resolution of Unresolved Items
ML20059M8351990-06-13013 June 1990
Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl
ML20248E9161989-10-12012 October 1989
Advises That Licensing Activities Associated W/Nrc Bulletin 88-004,considered Complete
ML20248D3591989-09-25025 September 1989
Forwards Amend 10 to Indemnity Agreement B-70,reflecting Changes to 10CFR140,effective 890701
IR 05000317/19890191989-09-22022 September 1989
Forwards Safety Insp Repts 50-317/89-19 & 50-318/89-20 on 890807-11.No Violations Noted
ML20247Q2781989-09-21021 September 1989
Forwards Safety Insp Repts 50-317/89-21 & 50-318/89-21 on 890818 & Notices of Violation & Deviation
ML20247P6701989-09-20020 September 1989
Forwards Request for Addl Info Re Util 890525 Response to Generic Ltr 88-14, Instrument Air Supply Problems Affecting Safety-Related Equipment. Info Requested within 35 Days of Ltr Date
ML20247P6611989-09-18018 September 1989
Requests Addl Info Re Generic Ltr 88-05, Boric Acid Corrossion of Carbon Steel Reactor Pressure Boundary.... NRC Should Be Notified of Full Implementation of Program within 30 Days Following Implementation
ML20247Q2371989-09-15015 September 1989
Requests Addl Info Re Util 890502 Response to Generic Ltr 89-08 Re Implementation of long-term Erosion/Corrosion Monitoring Program to Ensure Structural Integrity of All & Two Phase high-energy Carbon Steel Sys at Plant
ML20247G2841989-09-13013 September 1989
Approves 890207 Request to Withhold CEN-382(B)-P, Verification of Acceptability of 1-PIN Burnup Limit of 60 Mwd/Kg for Calvert Cliffs,Units 1 & 2 from Public Disclosure (Ref 10CFR2.790)
ML20247E8311989-09-0909 September 1989
Requests Util Furnish Ref Matl in Encl List, Ref Matl Requirements for Reactor/Senior Reactor Operator Licensing Exam, by 891004.Written Exam Scheduled for 891204 & Operating Exams Scheduled for 891205-08
ML20246Q1781989-09-0505 September 1989
Discusses Conclusions of Investigation 1-89-003 Re QC Inspector Harassment & Intimidation by Craft Personnel. Insufficient Evidence Found to Conclude Incidents Constitute Violation of 10CFR50.7.Response Requested within 30 Days
ML20246K1251989-08-31031 August 1989
Ack Receipt of & Payment of Civil Penalty in Amount of $75,000,proposed by NRC in
ML20246L3301989-08-28028 August 1989
Forwards Insp Repts 50-317/89-14 & 50-318/89-14 on 890516-0703 & Notice of Violation.Mgt of Surveillance Programs Has Been Source of Continuing Concern to NRC
IR 05000317/19890121989-08-24024 August 1989
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-317/89-12 & 50-318/89-12
ML20246G1221989-08-22022 August 1989
Forwards Safety Insp Repts 50-317/89-17 & 50-318/89-18 on 890717-21 & Notice of Deviation
1990-09-07
[Table view]
Category:OUTGOING CORRESPONDENCE
MONTHYEARML20138H3831999-10-25025 October 1999
Forwards Draft Model of Renewed License for Calvert Cliffs, Unit 2 to Illustrate How List of Minimum Requirements Could Be Incorporated Into License Condition
ML20217M1721999-10-19019 October 1999
Forwards NRC Rept Number 17, Requal Tracking Rept Form Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates
ML20212M2631999-10-0404 October 1999
Informs That Staff Concluded That Licensee Responses to GL 97-06 Provides Reasonable Assurance That Condition of Util SG Internals in Compliance with Current Licensing Bases for Calvert Cliffs Nuclear Power Plant
ML20212J7811999-09-30030 September 1999
Requests That Licensee Address Potential Aging Mgt Issue Re Effects of Void Swelling of Rv Internals by Making Plant Specific Commitment to Implement Focused age-related Degradation Insp for Evidence of Void Swelling in Future
ML20212J5611999-09-29029 September 1999
Informs That on 990916,NRC Completed mid-cycle Plant Performance Review of Calvert Cliffs.No Areas in Which Util Performance Warranted Addl Insp Beyond Core Insp Program Identified.Historical Listing of Plant Issues,Encl
ML20212A2001999-09-0808 September 1999
Forwards Insp Repts 50-317/99-06 & 50-318/99-06.Two Violations Being Treated as Noncited Violations
ML20211N8971999-09-0707 September 1999
Responds to Ltr to D Rathbun of NRC Dtd 990720,in Which Recipient Refers to Ltr from Wc Batton Expressing Support on Renewal Application of Baltimore Gas & Electric Co for Calvert Cliffs Plants
ML20211K3091999-08-27027 August 1999
Informs That During 990826 Telcon,L Briggs & B Bernie Made Arrangements for NRC to Inspect Licensed Operator Requalification Program at Calvert Cliffs Npp.Insp Planned for Wk of 991025
ML20210Q1941999-08-11011 August 1999
Informs That Info Submitted in 981130 Application Re CEN-633-P,Rev 03-P,dtd Oct 1998,marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended
ML20210N1291999-08-0505 August 1999
Forwards NRC Response to W Batton Ltr Expressing Support of Renewal Application for Calvert Cliffs Plants as Requested in Ltr
ML20211C0951999-07-30030 July 1999
Expresses Appreciation for Participation in Y2K Training & Tabletop Exercise Held on 990714
ML20210J0741999-07-30030 July 1999
Expresses Appreciation for Participation in Y2K Training & Tabletop Exercise on 990714.Suggests Referral to NRC Y2K Web Site to View Issues & Lessons from Tabletop That Will Be Tracked by Nrc.Web Site Should Reflect Info within 2 Wks
ML20211C3251999-07-30030 July 1999
Expresses Appreciation for Participation in Y2K Training & Tabletop Exercise Held on 990714
ML20211B5381999-07-30030 July 1999
Expresses Appreciation for Support in Y2K Training & Tabletop Exercise Held on 990714.Suggests Referral to NRC Y2K Web Site to View Issues & Lessons from Tabletop That Will Be Tracked by NRC
ML20210D0911999-07-22022 July 1999
Responds to to Chairman Jackson Referring to Ltr from New 7th Democratic Civic Club,Inc.Forwards Staff Response to W Batton,President of New 7th Democratic Civic Club,Inc
ML20210A5021999-07-20020 July 1999
Responds to ,Expressing Support for Renewal of Operating Licenses for Calvert Cliffs Plant & to Concerns Re Lack of Specificity for License Renewal Regulations & Length of Time Set Aside for Public Comment
ML20210B7651999-07-15015 July 1999
Forwards SER Denying Licensee Proposed TS Amend Dtd 981120, to Delete TS Requirements for Tendon Surveillance & Reporting Because TS Requirements Duplication of Requirements in 10CFR50.55a.Notice of Denial Encl
ML20209G2081999-07-13013 July 1999
Forwards Insp Repts 50-317/99-05 & 50-318/99-05 on 990509- 0626.No Violations Noted
ML20210A6311999-07-0606 July 1999
Discusses Closure of TACs MA0532 & MA0533 Re Response to Requests for Addl Info to GL 92-01,rev1,suppl 1, Reactor Vessel Structural Integrity, for Plant,Units 1 & 2
ML20211H8431999-06-23023 June 1999
Ack Participation of Calvert Cliffs Nuclear Engineering Dept in NRC Cooperative Research Project with Univ of Virginia. Copy of Relevant Portion of NRC Cooperative Agreement with Univ of Virginia Encl
ML20196C6831999-06-21021 June 1999
Discusses Proposed Alternative Submitted by Bg&E for Calvert Cliffs NPP to Requirements of 10CFR50.55a(g)(4) in Regard to Compliance with Latest Approved Edition of ASME Code,Section XI for Third Ten Year Insp Interval Beginning on 990701
ML20196E0371999-06-16016 June 1999
Forwards Insp Repts 50-317/99-03 & 50-318/99-03 on 990321-0508.Apparent Violation Being Considered for Escalated Enforcement Action
ML20207G4331999-06-0707 June 1999
Informs That in Response Request by Nrc,Fema Evaluated Adequacy of Evacuation Plans & Training of Local First Responders for Area Around Ccnpp.Copy of FEMA & Encl to Ltr,Which Provides FEMA Recommendations Encl
ML20207G4701999-06-0707 June 1999
Informs of Reorganization in NRR Ofc,Effective 990328. Organization Chart Encl
ML20207B2491999-05-21021 May 1999
Forwards Insp Repts 50-317/99-04 & 50-318/99-04 on 990405-16.No Violations Noted.Insp Revealed Few Potential & Plausible Aging Effects NRC Team Determined Should Be Included in License Renewal Application
ML20207C0321999-05-18018 May 1999
Forwards Fifth Rept Which Covers Month of Apr 1999. Commission Approved Transfer of TMI-1 Operating License from Gpu to Amergen & Transfer of Operating License for Pilgrim Station from Beco to Entergy Nuclear Generating Co
ML20206A6171999-04-22022 April 1999
Responds to Request for Statistics on Allegation Re Plant by J Osborne.Encl Tables Provides Breakdown of Allegations by Source Category for Allegations Receive in CY95-98 & First Six Month of 1999
ML20205R0961999-04-15015 April 1999
Forwards Insp Repts 50-317/99-01 & 50-318/99-01 on 990131- 0320.One Violation of NRC Requirements Identified & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy
ML20205P1381999-04-0909 April 1999
Discusses 990223 Ppr.Forwards Plant Issues Matrix & Insp Plan.Since Spring 1998 Unit 1 Operated at Essentially Full Power.Unit 2 Had Similar Power History Except for Jul 1998 Manual Reactor Trip Due to Small Bore Pipe Steam Leak
ML20205P1281999-04-0808 April 1999
Forwards Monthly Status Rept on Licensing Activities & Regulatory Duties of NRC for Mar 1999.Targets for Licensing Action Age & Completion Rates & License Renewal Process for Calvert Cliffs Remains on Schedule
ML20205E5511999-03-26026 March 1999
Forwards Insp Repts 50-317/99-02 & 50-318/99-02 on 990208-12.No Violations Noted.Insp Was First of Three Planned Visits to Verify Ccnpp License Renewal in Compliance with Requirements of Rule for License Renewal
ML20205G8841999-03-24024 March 1999
Discusses Bg&E Application Filed on 980408 for Renewal of Operating Licenses DPR-53 & DPR-68 for Calvert Cliffs Units, 1 & 2.For Listed Reasons,Partial Exemption from 10CFR170 Fees Granted IAW 10CFR170.11(b)(1)
ML20205B0291999-03-24024 March 1999
Informs That Author Determined That Partial Exemption from 10CFR170 Fee Requirements Appropriate for Footnote 4 of License Renewal Application for Plants,Units 1 & 2,dtd 980408,that Staff Determines Has Generic Value to Industry
ML20204H6281999-03-21021 March 1999
Forwards SER Reflecting Status of Staff Review of Util License Renewal for Calvert Cliffs Nuclear Power Plants, Units 1 & 2
ML20207E9641999-03-0404 March 1999
Forwards Insp Repts 50-317/98-12 & 50-318/98-12 on 981213- 990130 & Notice of Violation Re Failure of Maint Workers to Tighten Bolting for Svc Water Heat Exchanger
ML20207G8631999-02-25025 February 1999
Forwards Operator Initial Exam Repts 50-317/99-301OL & 50-318/99-301OL on 990122 & 25-29 (Administration) & 990201- 05 (Grading).All Applicants Passed All Portions of Exams
ML20203D3981999-02-0505 February 1999
Forwards Safety Evaluation Accepting Procedure Established for long-term Corrective Action Plan Related to Containment Vertical Tendons
ML20203A6141999-02-0303 February 1999
Submits Details on Listed Areas Re Inspection Plan of Insp Scheduled for 990203
ML20202J1901999-01-28028 January 1999
Discusses License Renewal for Operating Power Reactors.Two Applications Received for Renewing Operating Licenses. Commission Established Adjudicatory Schedule Aimed at Completing License Renewal Process in 30-36 Months
ML20202H7621999-01-28028 January 1999
Discusses Guidance Re License Renewal for Operating Power Reactors Developed in Response to FY99 Energy & Water Development Appropriations Act Rept 105-581
ML20199G4121999-01-20020 January 1999
Forwards SE Accepting Util USI A-46 Implementation Program for Plant
ML20199K8481999-01-19019 January 1999
Forwards Insp Repts 50-317/98-11 & 50-318/98-11 on 981025-1212.No Violations Noted
ML20199L6621999-01-19019 January 1999
Informs That Licensee Authorized to Administer Initial Written Exam to Listed Applicants on 990122.NRC Region I Operator Licensing Staff Will Administer Operating Test to Applicants
ML20199F4101999-01-0808 January 1999
Forwards SE Accepting Util 960213,0725 & 981202 Responses to GL 95-07, Pressure Locking & Thermal Binding of Safety- Related Power-Operated Gate Valves
ML20198S4291999-01-0707 January 1999
Requests Addl Info Re License Renewal Application as Application Relates to Staff Position on Environ Qualification
ML20198S7491999-01-0707 January 1999
Forwards SER Accepting Licensee ,Suppl by 980424 & 1124 Ltrs Proposing Changes to Rev 49 of Calvert Cliffs Nuclear Power Plant Quality Assurance Program Description in Accordance with 10CFR50.54(a)(3)
ML20196K2991999-01-0404 January 1999
Forwards Notice of Consideration of Approval of Transfer of Facility Operating License & Matl License & Opportunity for Hearing in Response to Application
ML20202D0271998-12-15015 December 1998
Forwards Notice of Withdrawal of Application for Amend to License DPR-69.Proposed Change Would Have Modified Svc Water Head Tanks.Without Encl
ML20198L3431998-12-12012 December 1998
Forwards Insp Repts 50-317/98-10 & 50-318/98-10 on 980706-10 & 1118.Insp Rept Documents App R Issues Which Constituted Violations of NRC Requirements.Nov Not Issued Because, Violations Identified by Licensee Staff as Part of C/A
ML20198B1791998-12-10010 December 1998
Advises of Planned Insp Effort Resulting from Calvert Cliffs NPP Review Conducted on 981110.Details of Insp Rept for Next 6 Months & Historical Listing of Plant Issues Considered During Process Encl
1999-09-08
[Table view] |
Text
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MAR 2 01986 Docket Nos. 50-317 License Nos. DPR-53 50-318 DPR-69 Baltimore Gas and Electric Company ATTN: Mr. J. A. Tiernan Vice President Nuclear Energy P. O. Box 1475 Baltimore, Maryland 21203 Gentlemen:
Subject: Combined inspection 50-317/85-31 and 50-318/85-26
! This refers to your letter dated January 13, 1986, in response to our letter dated December 13, 198 Thank you for informing us of your plans regarding the resolution of open items related to control room habitabilit Your cooperation with us is appreciate
Sincerely, OS31sn1 SI-- :c 9f:
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o s art n, Directo Division of Radiation Sa y and Safeguards CC:
M. Bowman, General Supervisor, Technical Services Engineering :
Thomas Magette, Administrator, Nuclear Evaluations l Public Document Room (PDR) l Local Public Document Room (LPOR) l Nuclear Safety Information Center (NSIC) i NRC Resident Inspector !
State of Maryland (2) l l
.
R603280171 860320 I PDR ADOCK 05000317 O PDR OFFICIAL RECORD COPY RL CC 85-31/26 - 0001. /12/86 s l l
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J Baltimore Gas and Electric'
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Region I Docket Room (with concurrences).
! DRP Section Chief M. McBride, RI, Pilgrim T. Kenny, SRI, Salem D..Jaffe, LPM, NRR
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BALTIMORE g GAS AND ELECTRIC CHARLES CENTER P. O. BOX 1475 * BALTIMORE, MARYLAND 21203 JOSEPH A.TIERNAN Vect PatstDENT NucLEAn ENERGY January 13, 1986 U. S. Nuclear Regulatory Commission ~ Docket No Region I 50-318 631 Park Avenue License No DPR-53 King of Prussia, PA 19406 DPR-69 ATTENTION: Mr. Thomas T. Martin, Director Division of Radiation Safety & Safeguards Gentlemen:
This refers to Inspection Report 50-317/85-31, 50-318/85-26; which identified apparent deficiencies in the area of Control Room Habitability. We have conducted a thorough review of the findings and have worked with Mr. P. Clemons of your office previously in this are Enclosure (1) to this letter is a written statement in reply to those findings noted in your lette Based on the information provided in Enclosure (1), we request you reevaluate the appropriate findings. Should you have further questions regarding this reply, we will be pleased to discuss them with yo Very truly yours, 3AT/SRC/gla Enclosure cc: D. A. Brune, Esquire G. F. Trowbridge, Esquire D. H. Jaffe, NRC T. Foley, NRC '
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t ENCLOSURE (1)
REPLY TO APPENDII A OF IEtC INSPECTION REPORT 50-317/8 5L31; S0-318/85-26 FINDING 317/8 5L31-01 We plan to measure the isolation damper and access door leakage rates, in addition to estimating the leakage rate in the duct
. work outside the Control Room envelope . A total inleakage rate l will then be estimated and, if necessary, used in a new dose calculation for Control Room Operator We will provide the i results of the inleakage determination and dose calculation by l February 1,198 We will determine any appropriate corrective action, if
- necessary, when deficiencies are note FINDING 317/8 5L27-01; 318/8 542 5L01 l The following maintenance deficiencies have been corrected
oCracked panels in the air handling unit have been repaired (welded),
oAir leaks at the cooling coil penetrations have been sealed, and oLatches on duct windows have been replace In addition to the missing screws and bolts, and holes at stress l points on the fabric expansion joints, the following deficiencies were noted during the walkdown of affected ductwork:
oCrack in a panel for #12' Air Handling Unit, and oMissing plugs in test penetration holes in the
'
ductwor These deficiencies will be corrected by April 1, '198 ; FINDING 317/8 5631-02 Licensee Event Report 8 5-014 (Unit 1) documented specific issues ;
in this findin The -louvered dampers were repaired and shut o '
a Control Room high radiation signa The following corrective actions were taken:
oBroken blade brackets were replaced, oDamper linkages were adjusted, and oA sampling of similar dampers were inspecte We intend to evaluate the isolation capability of the louvered dampers by measuring the leakage through these dampers in the recirculation mode with the butterfly dampers open. This evaluation should be completed by April 1, 198 <
