IR 05000443/1993018

Insp Rept 50-443/93-18 on 930927-1001.No Violations Noted. Major Areas Inspected:Fire Protection Program & Implementation in Areas of Administration Controls, Surveillances,Combustible Controls,Testing & Audits

ML20059C166
Person / Time
Site:	Seabrook
Issue date:	10/20/1993
From:	Easpen P, Finkel A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20059C155	List: IR 05000443/1993018 ML20059C153
References
50-443-93-18, NUDOCS 9311010037
Download: ML20059C166 (11)

Text

{{#Wiki_filter:. . . U.S. NUCLEAR REGULATORY COMMISSION

REGION I

REPORT NO: 50-443/93-18 DOCKET NO: 50-443 LICENSE NO: NPF-86 LICENSEE: North Atlantic Energy Service Corporation Seabrook Station Unit No.1 Post Office Box 300 Seabrook, New Hampshire 03874 > FACILITY NAME: Seabrook Station Unit No.1 INSPECTION AT: Seabrook, New Hampshire INSPECTION DATES: September 27,1993,through October 1,1993 /kN INSPECTOR:

A. Finkel, Senip/r Reactor Engineer Date ' Performance Programs Section , Operations Branch, DRS < i esk hd-h1-d& ~ APPROVED BY: Plackeel Eapen, Chief Date Systems Section Engineering Branch, DRS t i 9311010037 931021 PDR ADOCK 05000443 G pyg . _ _ . -

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' Areas insoccted: Announced safety inspection of the Fire Protection Program and its implementation in the areas of Administrative Controls, Surveillances, Combustible Controls, Testing, Audits, Brigade Training, Firewatches Program and followup on fire program open items and NRC Information Notice.

Results: No safety issues were identified with the fire protection equipment, system, or > program. The fire detection surveillance, control of combustibles, fire brigade training and - drills and fire audits are being conducted as described in the site fire protection plan. The fire protection system for the site is in an operational mode with a dedicated firewatch performing a firewatch inspection as part of their site rounds program. The licensee has approximately ten locations in their fire watch program at this time. Fire protection open items are evaluated and classified on a timely bases. As part of a self-initiative program in the fire area, the licensee has been replacing sections of their fire system schedule 40 piping for the last few years and have nearly completed the pipe replacement task. Also, a new microprocessor-based fire alarm system is being installed to replace their present fire alarm system.

The fire protection piping replacement program and the microprocessor-based fire alarm - system are self-initiative programs that the licensee implemented to improve their existing fire system. The inspector's review of these two programs indicates that both programs are supported with detailed engineering data for selecting these designs. The Simplex fire detection system is a state-of-the-art microprocessor-based digital / addressable fire alarm

system.

A review of Qualification Report No. 86-79 (Twin City Report No. 414186-969) indicates that the 3M Company Interam E-50 Fire Barrier System materials, when applied to conduit installations, are qualified for a 1 hour fire-rated value based on the ASTM E-119 Fire Test.

j The Seabrook site does not use the 3M Interam E-50 materials as a 1 hour fire barrier material on cable trays; therefore, the licensee indicated that NRC Information Notice 93-41 was not applicable at this site.

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. H . l' DETAILS 1.0 PERSONS CONTACTED Attachment 1 provides a listing of persons contacted during the inspection.

2.0 FIRE PROTECTION PROGRAM (64704)'

2.1 Introduction An inspection was performed to evaluate the adequacy of the licensee's fire protection program and associated implementing procedures. The inspection included verification of procedure implementation, technical adequacy of procedures and programs, inspection of plant fire facilities, fire brigade training status, firewatch personnel qualifications and program requirements, manpower assignments and review of the licensee's audit program.

Surveillance and routine testing, administrative and other procedures related to the implementation of the fire program were reviewed by the inspector to measure the effectiveness of the fire protection program.

2.2 Plant Tour The inspector toured accessible vital and nonvital areas of the site and visually inspected the fire protection water systems, fire pumps, fire water piping and distribution systems, post-indicator valves, yard hydrants, contents of fire protection equipment storage cabinets, and the condition of the fire brigade equipment. The tour also included the inspection of the various types of fire detectors, alarm panels, positions of automatic and manual fixed suppression instruments, interior plant fire hose stations, fire barrier penetrations, fire doors, and discussions with firewatch personnel encountered during the tour. The inspector determined that the firewatch personnel were well trained and knowledgeable of their firewatch requirements. The inspector noted that the fire protection equipment was in an operational status; and, where there was an item of fire protection equipment not operating, it was identified with a deficiency tag, and it was part of the firewatch program. Fire equipment tank gauges indicated correct levels as described in their procedures and battery powered lights tested during the tour were in working order. During the plant tour, the inspector noted that all fire doors were closing and latching automatically. Also during the tour, the inspector noted that a new jockey pump had been installed to replaced the casting failures of the originally installed jockey pumps. Replacement jockey pumps have been ordered; however, they had not arrived on site during this NRC inspection period.

i -{ 'The parenthetical notations following the paragraph title denotes the NRC inspection procedure that was used by the inspector in conducting this inspection, i ~

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3.0 DOCUMENTS AND PROGRAMS REVIEWED The fire protection program documents listed in Attachment 2 of this report were used by the , ! inspector in performing the inspection of the fire program at this site. The licensee's fire program polices, procedures, drills and analyses reviewed by the inspector appeared to be technically sound and properly implemented. No violations or unresolved items were identified.

, 4.0 FIRE DETECTION INSTRUMENTATION SYSTEM The existing fire alarm system is being replaced with a Simplex 4100 and 4100+ { microprocessor-based digital / addressable fire alarm system. The Simplex detector base has { an eight digital binary address switch system that allows each detector to be coded with its j own address code. The system will have six fire control panels and a cathode ray tube (CRT) display. A master control panel is located in the control room with other control

panels located in the Control Building, Turbine Building, Diesel Building, PAB, EFW Building and the Electrical Tunnels. The detectors will be calibrated and tested from each control panel that they are connected to. The control room panel is capable of testing the entire system. The first phase of the replacement program will replace approximately half-eight hundred - of the existing Pyrotronic fire detectors and detector bases and approximately fifty manual pull stations. The inspector reviewed the test results of forty eight detectors during a location and type test run that was conducted on September 21,1993. The test verified that each detector was in its correct position and the sensitivity values were within their assigned tolerances as described in the fire logic diagrams. All detectors will be replaced with the Simplex detectors with the exception of the ultraviolet flame detectors located above the Diesel Generators (DG). UL listed digital addressable flame detectors are not available at this time. A zone isolation module (ZIM) will be installed in the existing DG building panels FP-CP-412 and 413. The system block diagram is described in drawing 1-NHY-506474, "FP-Digital Fire Detection Control Loop Diagram." The six flame detectors will alarm as one addressable location. Since these detectors are located above each Diesel Generator and the DG's are in the same area, one alarm message should send the fire fighters to the correct area. This system will be verified during the fire system acceptance test.

5.0 FIRE SYSTEM PIPING REPLACEMENT PROGRAM As part of a self-initiative program, the licensee started replacing their schedule 40 piping in the fire system. The fire system piping replacement program, as part of a preventative maintenance program, was a fire program initiative started by the fire engineering staff. The inspector selected the piping in the Fire Pump Main Booster Pump section of the fire system piping for inspection verification of the work package requirements for this installation. The replacement pipe sections were installed during early 1993. The inspector verified that the { . _ _ _ _.

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piping was installed, inspected, and tested as described in the installation drawings and , documented in the fire system work order documentation. The licensee's program controls

on the fire piping replacement task indicate that the work is nearly completed.

6.0 FIRE BRIGADE TRAINING AND DRILLS f Fire Department training procedures and attendance records for brigade members were reviewed by the inspector. The records were complete and maintained in an up-to-date

status. The inspector verified that the fire brigade members listed on the August 1993, " Fire Brigade Qualification Status Listing," have completed their required fire training courses including their hands-on training program at the fire school. Discussions with fire brigade members during the site inspection indicated that the fire brigade members are cognizant of their responsibilities and that the training they are provided is beneficial in maintaining their awareness of current developments in fire protection and fire fighting techniques. There are approximately 45 qualified members listed on the Fire Brigade Qualification Status Listing.

l This is an adequate number of qualified fire brigade personnel to support the licensee's shift operation, which requires thirty to thirty-six qualified personnel.

7.0 FIREWATCII PROGRAM The shift firewatch personnel are assigned their shift assignments from the assigned control room Unit Shift Supervisor or the Fire Brigade Leader. Permanent assigned personnel perform the firewatch task for this site. The fire protection supervisor is notified of the daily firewatch requirements from the Unit Shift Supervisor. The firewatch personnel, as part of their rounds, inspect the assigned firewatch areas and record the firewatch area locations on a i digital readout recorder. The fire protection technician verifies that the firewatch personnel.

performed their required shift assignments by reviewing the digital recorder results at the end of each shift. In conjunction with the digital recorder, the fire protection technicians audit the firewatch personnel during the shift. The inspector verified that the ten locations requiring a firewatch were verified by the firewatch personnel and documented in their digital recorder during a firewatch shift review on September 29,1993. The inspector also reviewed the firewatch personnel training records to ensure that they have received their required firewatch training.

8.0 AUDITS OF FIRE PROGRAM The inspector reviewed the latest annual audit report (No.93-A08-01) performed on the fire protection program plan and system equipment from August 30 through September 3,1993.

The 1993 audit report identified five findings and two observations. All fmdings described in the audit report have been addressed by the licensee in a prompt time period. The audit findings had no effect on the operation of the fire protection system or equipment but were associated with program responsibility, procedures and fire drills. The inspector also noted I that the fire program had been divided among various organizations at the site. The licensee has corrected this division of fire responsibility by establishing that the Fire Protection i - - .

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i Supervisor will hold monthly fire program meetings with the site organizations to insure that

the fire protection program requirements are being performed as stated in the plan. Also, i site management is to issue a procedure defining the responsibilities and functions of the Fire Protection Supervisor.

The fire protection Triennial and Biennial audit (No. 92-A08-01) was conducted from July 27

through July 30,1992. The results of the audit stated that, "the Fire Protection Program was ' adequate and effective as no findings or observations were identified for those portions governed by the Station's Fire Protection Program."

The inspector verified that the audit report findings (No. 93-A08-01) did not identify any safety issue with the operation of the fire system or fire equipment. The inspector also , verified that the audit findings have been closed by the assigned organizations in a timely manner. The licensee also plans to issue a document to address the responsibilities of the , Fire Protection Supervisor.

, . 9.0 FIRE EQUIPMENT TESTING The inspector reviewed the following fire protection equipment surveillance test procedures and test results to verify that the fire system equipment was in conformance with the - requirements of the Technical Specification and that the system was in an acceptable l operational status. A review of the last six months' test results indicated that the equipment ' met the test procedure acceptance requirements with no indication of system degradation.

! - OX0443.01 Diesel Fire Pump Weekly Test - OX0443.02 Electric Fire Pump Weekly Test - - OSO443.74 Annual Fire Pump Flow Test to 150% of Rated Capacity l - OX0443.0618 Month Fire System Functional Test , The trend data reports on the results of the above tests indicated that their is no system degradation in the fire system at this time.

A review of the Yard Hydrant and Barrel Semi-Annual surveillance procedure (0N0443.59) i - and test results indicated that all yard fire hydrants and associated hydrant hose houses met < ] the requirements of the surveillance procedure. The next surveillance test is scheduled to ! start on October 12, 1993.

The licensee has a check valve program that is described in Procedure No. ES1850.001,

i " Check Valve Performance Monitoring Program;" however, the Fire Diesel Pump check valve is not in the program described in Procedure ES1850.001. The Fire Protection Engineering staff stated that the manufacturer of their Fire Diesel system check valve has no , scheduled or required maintenance program on their valve.

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10.0 NRC INFORMATION NOTICE 93-41 (92701) The subject of NRC Information Notice (IN) 93-41 describes the NRC's review of the one hour fire endurance test results for Thermal Ceramics Kaowool,3M Company FS-195 and 3M Company Interam E-50 Fire Barrier Systems materials. The NRC has some concern with the use of the 3M Company Interam E-50 fire barrier system based on the results as described in a Twin City Corporation Test report of September 1986 when installed on a , cable tray system. The Seabrook site has installed the 3M Company Interam E-50 Fire , Barrier material on approximately 65 steel conduits and junction boxes. The Fire Protection Engineer (Memorandum No. 930557, August 25,1993) stated that the test results to date do not indicate any inability of the Seabrook design to meet its design function.

The NRC inspector reviewed the qualification test results of Fire Test Report No. 86-79, July 1,1986, that was performed on 5 inch conduit (Aluminum / steel), including a junction box. This test report, which is documented in Twin City Report No. 414186-969, tested 5 inch conduits using three layers of E-53A on a 5 inch Aluminum and steel conduit and three layers of E-53A on a junction box.

The fire test for the above design configuration was performed to the 1 hour requirement of ASTM E-119 fire temperature curve. This test requires that a temperature of 1700 F (927"C) on the surface of the test sample will be reached within I hour. To pass this, the temperature on the test sample protected by the material shall not exceed the following requirements: . - Average internal temperature will be ambient F + 250 F - Maximum internal temperature will be ambient F + 325 F The test results for the above conduit configuration described in the Fire Test Report No.

' 86-79 is described as follows: Cable Templ"F) At End Of I Hour Max. Ayn Min.

- 5 inch Aluminum Conduit 211 188 124

- 5 inch Steel Conduit 218 179 140 - Junction Ik)x 211 210 209 e - Ambient Temp was 71 F . r .-.- _--- w-- .-- ..,-w,

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As can be seen from the above test results, the temperature on the cables within the test conduits were well within the ASTM E-119 requirements. After the temperature test was completed, a test was performed on the cables, within the conduits, to test for cable conductors shorting to ground and shorting to each other. The cables passed both these tests.

A visual examination of the cables indicated that no blistering, charring, melting, and no , noticeable deterioration of and insulation or cable jacketing was identified. The installation configuration for the conduit and junction box was described in Appendix E (Quality i

Assurance) of the test report.

As stated above, the Seabrook site has a combination of 65 steel conduits and junction boxes covered with the 3M E-53 A material. The Seabmok conduit and junction box design is described in drawing HLS/VB-1, April 15,1986, and in design basis document (DBD)-FP-06, Table IV, Fire-Rated Wrapped Conduits.

One difference in the Seabrook installation design from that of the 3M qualification test , sample is that the Seabrook design uses four to five layers of E-53A while the qualification , test was performed with three layers of E-53A. Also, the Seabrook installation of the E-53A was form fitted to the conduit with at least a 2 inch overlap of the E-53A material, thus eliminating the need to use the CP-25 Caulk material that was used in the 3M qualification test.

, f 10.1 Water Hose Stream Test After the temperature test of the 3M E-54 material was completed, an ASTM E-119 water hose stream test was performed. Test report No. 414186-969 indicated that both the inner and outer layers of the E-54A material were partially torn on the cable tray installation within 30 seconds of the 2% minute water hose stream test cycle. The Fire Protection ' Engineer determined that cables within the Seabrook conduits should not be adversely affected by the tearing of the E-53A that occurred during the water hose stream test that was performed on the 3M cable tray installations.

+ The Seabrook Fire Protection Engineer plans to monitor the NRC position associated with NRC IN 93-41; however, the licensee believes that their present use of the 3M E-53A ! material on their conduit and junction box designs is qualified to the 1 hour fire test described in ASTM E-119.

The NRC inspector's review of the above referenced qualification test results and the Seabrook installation of the 3M E-53A material on site conduits and junction boxes indicates ' that the Seabrook installation conforms to the designed qualified as described in paragraph 10.0 above. Based on the qualification test results described in Fire Test Report No. 86-79 and the Seabrook conduit and junction box installations, the inspector agreed that the 3M E53A material provides a qualified I hour rated fire barrier installation.

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11.0 LICENSEE CORRECTIVE ACTION REPORT (92701) . Licensee corrective action report No. SIR No. 93-82 describes the activation of the Generator Step-up Transformers (GSU) fire deluge system due to false alarms, which were caused by the present Rate-of-Rise Ore detectors. Fire protection engineering has determined that the present installation on the GSU Transformers is a misapplication of the currently installed Dre detectors. The extreme temperature variations in the transformer area, due both to weather conditions and the operation of the transformers fans based on load factors, cause large temperature swings in this area. To reduce the activation of the present Rate-of-Rise detectors, the licensee has relocated specific detectors to a less temperature sensitive area on the GSU. A replacement type of GSU Ore detector is scheduled to be selected by engineering during October 1993, with a scheduled installation date to be established by the licensee. The activation of the GSU did not result in any manual or automatic actuation of any Engineered Safety Feature or the Reactor Protection System; however, the design and installation is being actively implemented by the licensee.

, 12.0 EXIT MEETING Licensee management was informed of the scope and purpose of the inspection at an entrance meeting conducted on September 27, 1993.

. The findings of the inspection were discussed periodically with licensee representatives during the course of the inspection. An exit was conducted on October 1,1993, at which time the Undings of the inspection were presented.

Attachments: 1. Persons Contacted 2. Documentation Review ,

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ATTACIIMENT 1 Persons Contacted i North Atlantic Enercy Service Corocration

• R. Anderson, OTG Manager
• D. Conti, Fire protection Supervisor
• W. DiProfio, Station Manager
• B. Drawbridge, Executive Director, Nuclear Production
• J. Grillo, Operations Manager
• R. Hanley, Operations Training Manager
• G. Kline, Technical Support Manager
• V. Pascucci, Quality Control Department Manager
• J. Peterson, Maintenance Manager
• J. Sobotka, NRC Coordinator
• E. Trump, Senior Fire Protection Engineer
• P. Tutinas, Engineering Supervisor
• J. Warnock, NS&A Manager United States Nuclear Reculator Commission
• R. Laura, Resident inspector
• Denotes those personnel attending the exit meeting of October 1,1993 The inspector also held discussions with managers, supervisors and other licensee employees during the course of this inspection including operations, technical, quality assurance and administrative personnel.

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ATTACilMENT 2 Documentation Reviewed Fire Detector Documentation Simplex 4100 and 4100+ Operating Manual (FA4-31-201) Simplex Panel Drawings FP-Cp-412 and 413 FP-Digital Fire Detection Control Loop Diagram 1-NHY-506474 ' Fire Protection Surveillance Procedures 0X0443.01, Diesel Fire Pump Weekly Test OX0443.02, Electric Fire Pump Weekly Test OXO443.06,18 Month Fire System Functional Test OXO443.74, Annual Fire Pump Flow Test to 150% of Rated Capacity ON0443.59, Yard Hydrant and Barrel Semi-Annual Test ES1850.001, Check Valve Performance Monitoring Program Oualification Reports For 3M Company E-50 Fire Barrier Materials Twin City Corporation Test Report, September 1986, No. 414186-969 Fire Test Report No. 86-79, Reference Report No. 414186-969 Seabrook Conduit and Junction Box design information, Drawing No. HLS/VB-1 ASTM E-119 Temperature and Water Hose Stream Test Requirements Fire Protection Memorandum No. 930557, August 25,1993 Seabrook Fire-Rated Wrapped Conduits, Table IV, Procedure DBD-FP-06 Fire Audit Reports Annual Audit Report No. 93-A08-01, August 30 through September 3,1993 Triennial and Biennial Audit Report No. 92-A08-01, July 27 through July 30,1992 Miscellaneous Fire Program Documents Muessco No.105-AP Globe Type Semi-Steel Check Valve Fire Brigade Training Qualification Record Cards (45 Cards Reviewed) , I l i )

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