IR 05000317/1981016
| ML20010H470 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 08/31/1981 |
| From: | Ebneter S, Koltay P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20010H465 | List: |
| References | |
| 50-317-81-16, 50-318-81-15, NUDOCS 8109240508 | |
| Download: ML20010H470 (8) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I 50-317/81-16 Peport No.
50-318/81-15 50-317 Docket No.
50-318 OPR-53 C
License No.
DPR-69 Priority
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Category C
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 Io.spection conducted: July 27-30, 1981
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Inspectors:
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$pcP.S.Koltay,ReactorInspector date' signed Approved by:
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S. D. EEneter, Chief, Plant Systems Section date' signed'
Inspection Summary:
Inspection on July 27-30, 1981 (Report Nos. 50-317/81-16 and 50-318/81-15)
Areas Inspected:
Routine unannounced inspection of the plant Fire Protection /
Prevention Program including:
administrative controls, fire brigade training, quality assurance, modifications to fire protec'. ion systems, fire protection i spection involved 30 equipment surveillance and critical fire areas. The n
inspector-hours onsite by one NRC regionally based inspector.
Results: No items of 'oncompliance were identified.
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Region I Form 12 (Rev. April 77)
f010924Ck3OS 8109tSi PDR ADO';K 05000317
.O PDR
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OETAILS 1.
Persons Contacted
- D. Buffington, Fire Protection Coordinator G. Campo, QC' Supervisor
- 0. Heibell, Supervisor, Technical Services R. Hunt, Fire Protection Engineer
- L. Weckbaugh, Engineer, Technical Services
- denotes those personnel who attended the exit interview.
2.
Fire Protection / Prevention Program-a.
Administrative Controls The inspector reviewed the following administrative procedures:
CCI 133B, Calvert Cliffs Fire Protection Plan, May 8,1980;
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CCI 126B, Administrative Control of Facility Change Requests, October 15, 1980; and, BG&E Safety Manual,1976.
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The inspector verified that the administrative procedures include:
(1) Control of Combustibles Prohibition on the storage of combustible, flammable or explosive hazardous material in safety-related areas.
Requirement for the removal of all wastes, debris, rags, oil spills or other combustible mat.erials resulting from the work activity following completion of the activity or at the end of each work shift, whichever is sooner.
Requirement-that all wood used in safety-related areas is treated with flame retardant.
Requirement for weekly inspecti n for accumulation of combustibles.
Special authorization for the use of combustible, flammable or explosive hazardous material in safety-related areas.
Instruction on the storage and movement of transient combustible materials in areas containing safety-related equipment.
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(2) Control of Ignition Sources Welding and cutting operations and other open flame ignition sources are controlled by work permit and are properly safeguarded in. areas containing safety-related equipment and components.
Smoking in safety-related areas is prohibited except where
" smoking permitted" areas have been specifically designated by plant management.
HoureKceping is properly maintained in areas containing safety-relatec equipment and components.
No items of noncompliance were identified.
b.
Fire Brigade Training The inspector reviewed the following documents:
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CCI 133B,Section IV, Fire Brigade Training;
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CCI 1338,Section VII, Fire Fighting Procedures;
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Fire Fighting Strategies for Plant Areas; and,
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Calvert Cliffs Fire Protection Program Evaluation, Section B.
The inspector noted that the licensee's r mcedure, CCI 1338,Section IV, allows licensee personnel to become fire brigade members upon completing an employee orientation course, approximately four hours, which does not include hands-on equipment training. A formal fire brigade training curriculum which is based on the guidelines contained in Attachment 2 of the NRC document titled, Nuclear Plant Fire Protection Functional Responsibilities, has been established, however, Procedure CCI 133B allows up to 2 years for brigade members to complete
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the course.
Presently, Procedure CCI 1338 allows the licensee to establish a fire brigade whose members did not receive training beyond employee orientat*on.
The inspector reviewed the qualifications of fire brigade members on several shifts and verified that at least three members of each brigade have completed the training curriculum, with remaining members receiving some classroom and hands-on equipment training.
The inspector also verified that all fire brigade members have participated in at least one fire dril.
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During the exit interview, the licene agreed to complete the training of all personnel who are r
,ently on the fire brigade, maintain a minimum of five fully +.ined personnel on each fire brigade, initiate a fire brigade leader training course, and rewrite Procedure CCI 133B to reflect initial training requirements detailed in the NRC document, Nuclear Plant Fire Protection Responsibilities.
This item is considered unresolved pending NRC review of the licensee's corrective action.
(317/81-16-01; 318/81-15-01)
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c.
Quality A;surance The inspector reviewed the following documents:
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QA Manual, Revision 1, May 12, 1981;
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Quality Assurance Procedure, QAP-9, Fire Protection, March 9, 1981; and,
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CCI 133B,Section X, Quality Assurance.
The inspector noted that Section 7 of QAP-9, Control of Purchased Material Equipment and Services, allows the licensee to verify quality of purchased material equipment and services by post insta'ila-tion testing. The procedure does not comply with the Nuclear.Regula-tory Guidance which is contained in Attachment 6 of the Nuclear Plant Fire Protection Responsibilities which requires that measures shall be established to assure that purchased material, equipment and services conform to procurement documents.
Thus, requirements for the use of equipment such as Underwriters Laboratories Listed and/or Factory Mutual Approved devices, the installation of such devices in accordance with applicable National Fire Protection Association Codes and deviations from the above are not controlled through the quality assurance procedura QAP-9. By review of fire protection system installations, the inspector verified, as outlined in Section 2.d of this report, that the installations are in accord-ance with NFPA codes and appropriate equipment has been utilized.
The licensee agreed to review QAp-9 and make appropriate changes to reflect the NRC guidelines.
(317/81-16-02; 318/81-15-02)
d.
Codes and Standards
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The inspector conducted a sample review of fire suppression and detection systems' specifications and drawing plus inspection-of randomly selected installed fire protection equipment. The inspector verified that the design and installation of equipment is in accord-ance with the applicable codes'and standards of the National Fire Protection Association (NFPA).
The inspected fire protection equipment is Underwriters Laboratories approved and/or Factory Mutual listed.
No items of noncompliance were identified.
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3.
Fi_re Protection Modification Required by Amendment Nos. 41 and 23 to Facility Operating License N'os. DPR-53 and DPR-69 Respectively
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Status of Fire Protection Modifications By review and examination of records including specifications and drawings and by examination of installad fire protection equipment, the inspector verified the licensee's implementation of scheduled modifications identified in the Safety Evaluation Report.
The licensee was granted schedular relief on several modifications identified in the SER.
a.
Completed Modifications The inspector verified that the following licensee modifications have been completed.
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SER Item 3.1.1, Curb in Diesel Room SER Item 3.1.2, Additional Fire Fighting Equipment
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SER Item 3.1.4, Marking of Fire Water Valves
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SER Item 3.1.5, Breathing Apparatus Recharging System
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SER Item 3.1.7, Fire Water System Valves
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SER Item 3.1.8, Miscellaneous Usage of Fire Water
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SER Item 3.1.10, Single Isolation of Fire Water Piping System
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SER Item 3.1.11, Portable Smoke Ejectors
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SER Item 3.1.13, Emergency Communications Facility Change Request 79-101
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SER Item 3.1.16, Control of Combustibles (See Paragraph 2)
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SER Item 3.1.18, Miscellaneous Protection for Control Room
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SER Item 3.1.21, Manual Hose Coverage Facility Change P.equest 79-1022
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SER Item 3.2.4, Ventilation Duct Penetrations
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Facility Change Request 79 1052, Fire Wall Modifications, including fire dampers and two Class A fire doors in rooms 524 and 526.
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SER Item 3.3.2, Emergency Lighting
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Facility Charge Request 79-1050 SER Item 3.3.4, C. Pump Lube Oil Collection System
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Facility Charge Request 79-1023. The containment building was not accessible to the inspector, thus physical verification of this system could not be made.
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SER Item 3.3.6, Fire Fighting Strategies SER Item 3.3.7, Quality Assurance Program. The licensee issued
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quality assurance procedure QAP-9, Fire Protection.
The inspector noted that the procedure does not follow NRC guidelines in several areas.
(See Paragraph 2.c)
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SER Item 3.2.5, Back Flow Protection.
Facility Change Request 80-1065, Diesel Generator Room Floor Drains No items of noncompliance were identified.
b.
Incomplete Modifications The inspector reviewed the following, partially completed modifications:
SER Item 3.1.3, Fire Water System Overpressurization.
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The inspector noted that the locked-in water pressute on wet type sprinkler system remains high, approximately 1/5-200 psi.
The licensee installed relief valves set at 200 psi on each system. The licensee is also, evaluating the possibility of reducing fire pumps discharge pressure.
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SER Item 3.1.6, Automatic Fire Suppression in the Cable Spreading Rooms.
Facility Change Request 79-1024. The inspector ;erified that the system installation is completed. However, the licensee has been unable to reach the required 7-10 percent concentration, during discharge tests.
SER Item 3.1.19, Fire Detection in Safety-Related Area
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Facility Change Request 79-1025 and 80-1008.
The inspector reviewed design drawings of irstallation of continuous thermal i
protection wire in reactor bui'dtr.g cable trays.
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4.
Facility Tc :r The inspector examined fire water piping and distribution systems, yard fire protection equipment, including valves, hydrants and contents of hose houses. During the inspection of the fire pump instaliation, the inspector noted that non-inuicating type valves have been installed on the pressure sensing lines of both fire pumps.
Inadvertent closure of the valves will prevent automatic pump start upon low system pressure.
This problem was brought to the licensee's attention who agreed to provide valve position indication, secure the valve in the open position and place the valves on the monthly valve inspection list. This item remains unresolved pending NRC review of the licensee's corrective action.
(317/81-16-03; 318/81-15-03)
In accordance with.smporary Instructions TI 2515/19, the inspector toured the following ::ritical fire areas: cable spreading room, cable chaser and auxiliary building corridors at elevations (-)10 ft. and 5 ft.
The inspector verified that the licensee has installed automatic suppression systems in all critical areas. Automatic sprinklers have been installed in the auxiliary building corridors and in four cable chases and automatic Halon 1301 suppression has bu:n provided in the cable spreading room and the associated cable chases. At the time of the ingection, the Halon system has not been satisfactorily tested.
The inspector toured all accessible vital and non-vital plant areas and verified that the licensee installed automatic sprinkler systems in the
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areas identified in licensee letter to NRR dated August 20, 1980, Changes to Fire Hazard Analysis.
5.
Review of Surveillance Test Records Associated with Technical Specification Requirements 4.7.11, Fire Suppression Systems The inspector selected and reviewed the following records to verify that the associated required Fire Protection Program Surve111ances had been performed and that the acceptance criteria had been mat.
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STP No. M-491-0, Fire Temperature Cetectors, February 27, 1981
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STP No. M-490-0, Smoke Detectors, March 13, 1981
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STP No M-691-0, Fire Suppression System Loop Flow Test, October 10, 1979
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STP No. M-696-0, Fire Pump Flow Test, April 6, 1981
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The inspector noted that surveillance procedure M-696-0 does not include Technical Specification requirement 4.7.11.1.le4, sequential starting of fire pumps.
The licensee stat.ed that the procedure will be revised to include the sequential pump start test.
This item remains unresolved pending NRC review of the licensee's corrective action.
(317/81-16-04)
6.
Unresolved Items Unresolved items are matters about which more information is required ta ascertain whether they are acceptable items, items of noncompliance,_or.
deviations.
Unresolved items disclosed during the inspection are discussed in paragraphs 2.b, 2.c, 4 and 5.
7.
Exit Interview The inspector met with the licensee rapresentatives denoted in Details (paragraph 1) at the site on July 30, 1981, and summarized the purpose and scope of the inspection findings.
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