ML18151A604

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Submits Technical Basis for & Requested NRC Approval of Continued Use of Thermo-Lag Radiant Energy Shields in Containment Relative to Requirements of 10CFR50 App R,Section III.G.2.f
ML18151A604
Person / Time
Site: Surry, North Anna  Dominion icon.png
Issue date: 04/22/1997
From: Ohanlon J
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
96-539, GL-86-10, IEB-92-001, IEB-92-1, IEIN-92-055, IEIN-92-55, IEN-92-55, NUDOCS 9704280200
Download: ML18151A604 (53)
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J VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 22, 1997 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY Serial No.

NL&OS/GDM Docket Nos.

  • License Nos.

NORTH ANNA AND SURRY POWER STATIONS UNITS 1 AND 2 RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION REGARDING RADIANT ENERGY SHIELD EXEMPTION REQUESTS96-539 R3' 50-280, 281 50-338, 339 DPR-32, 37 NPF-4, 7 In our letter dated December 15, 1995 (Serial No. 95-007B), Virginia Electric and Power Company submitted Appendix R Exemption Requests # 27 and 37 for Surry and North Anna Power Stations, respectively. These submittals provided the technical basis for, and requested NRG approval of, the continued use of Thermo-Lag radiant energy shields in containment relative to the requirements of 10 CFR 50 Appendix R, Section 111.G.2.f. In your letter dated October 15, 1996, you requested additional information to facilitate your review of the two exemption requests.

The NRG questions and our responses are provided in the enclosure.

No new commitments are intended as a result of this letter. If you have any questions or require additional information, please contact us.

Very truly yours,

~Po;!~

James P. O'Hanlon Senior Vice President - Nuclear Enclosure

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Regional Administrator U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, N.W.

Suite 2900 Atlanta, Georgia 30323 Mr. R. A. Musser NRC Senior Resident Inspector Surry Power Station NRC Senior Resident Inspector North Anna Power Station

RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION'.:REGARDlNG RADIANT ENERGY SHIELD EX.GMPTION REQUESTS REC 1n*-w/LTR DTD 04/22/97.... 9704280200

- NOTICE -

THE ATTACHED FILES ARE OFFICIAL RECORDS OF THE INFORMATION &

RECORDS MANAGEMENT BRANCH.

THEY HAVE BEEN CHARGED TO YOU FOR A LIMITED TIME PERIOD AND MUST BE RETURNED TO THE RECORDS & ARCHIVES SERVICES

. SECTION, TS C3; PLEASE DO NOT SEND DOCUMENTS CHARGED OUT THROUGH THE MAIL. REMOVAL OF ANY PAGE(S) FROM DOCUMENT*

FOR REPRODUCTION MUST BE

. REFERRED TO FILE PERSONNEL.

- NOTICE -

1 -

ENCLOSURE Response to NRC Request for Additional Information Regarding Radiant Energy Shield Exemption Requests # 27 and 37 Surry and North Anna Power Stations Units 1 and 2

Response to NRC Request for Additional Information Regarding Radiant Energy Shield Exemption Requests # 27 and 37 Surry and North Anna Power Stations Units 1 and 2 The following information is provided in response to the NRC's letter requesting additional information dated October 15, 1996. The NRC questions and our responses are as follows:

NRC Question (a)

The licensee indicated that the conduit wrap is provided until a distance of 20 feet of horizontal separation is achieved or until a rated fire barrier is encountered. Clarify if this conduit wrap is applied to the subject conduits until 20 feet of horizontal separation is achieved between the protected component/conduit and the intervening combustibles.

Virginia P!Jwer Response Figures 27-1 through 27-8 and Figures 37-1 through 37-8 for Surry and North Anna Power Stations, respectively, show the locations of the installed radiant energy shields, the relative locations of cable trays, and the location of the primary and alternate Appendix R circuits. (Also, see the descriptions provided in Attachments 1 through 4.)

Conduit wraps are applied on the subject conduits until there is 20 feet of horizontal separation between the "primary" and "alternate" Appendix R circuits. There are no intervening combustibles at these locations.

Cable trays are not considered to be intervening combustibles since firestops have been installed at these locations. The two tables provided below show the relationship between the "primary" and "alternate" instrumentation circuits relied upon to achieve compliance with Appendix R.

Additionally, the tables note that there are several other instrumentation circuits provided, that although not relied upon for Appendix R compliance, provide further redundancy for the primary instrumentation. This instrumentation is required for other purposes (e.g., Technical Specifications, Regulatory Guide 1.97, etc.).

There are three conduits protected by Thermo-Lag radiant energy shields at North Anna - two conduits for Unit 1 and one conduit for Unit 2. One conduit in Unit 1 is associated with Reactor Coolant System pressure and level transmitters 1-RC-PT-1000 and 1-RC-LT-1000. The entire length of the conduit is wrapped. The second Unit 1 conduit is associated with the Ex-Core Instrumentation System and is wrapped until 20 feet of horizontal separation with no intervening combustibles is achieved between the primary and alternate equipment.

The protected Unit 2 conduit is associated with Reactor Coolant System pressure and level transmitters 2-RC-PT-2000 and 2-RC-L T-2000. The conduit is wrapped in two separate locations: 1) between columns 5 and 6 and 2) from column 17 to the fuel building penetration where the conduit exits containment. The conduit is wrapped until 20 feet of horizontal separation with no 1 of 13

,) -

intervening combustibles is achieved between the primary and alternate equipment.

The conduit is not wrapped where a solid concrete floor provides separation between the primary and alternate equipment.

There are four conduits wrapped at Surry Power Station, two in each containment. The conduits in Unit 1 are associated with the Reactor Coolant System pressure and level transmitters 1-RC-PT-1449 and 1-RC-LT-1459A, respectively. The Unit 2 conduits are associated with Reactor Coolant System level transmitter 2-RC-L T-2459A and Steam Generator level transmitter 2-FW-L T-2487A. The conduits are wrapped until 20 feet of horizontal separation is achieved between the primary and alternate equipment with no intervening combustibles.

The two tables provided below show the relationship between the various containment instrumentation relied upon to achieve compliance with Appendix R.

In addition, Attachments 1 through 4 provide additional information on the location of the radiant energy shields within containment, as well as the general equipment layout.

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TABLE 1 INSTRUMENTATION CIRCUITS RELATING TO RADIANT ENERGY SHIELD APPLICATIONS SURRY UNIT 1 SURRY UNIT2 A. RCS PRESSURIZER A. RCS PRESSURIZER LEVEL INDICATION LEVEL INDICATION App. R "primary" train:

1-RC-L T-1461 2-RC-L T-2460 (Note 1)

(Note 2)

App. R alternative 1-RC-L T-1459A 2-RC-L T-2459A shutdown:

B. RCS PRESSURE INDICATION App. R "primary" train:

1-RC-PT-1402-1 (note 3)

App. R alternative 1-RC-PT-1449 shutdown:

B. STEAM GENERATOR LEVEL INDICATION App. R "primary" train:

2-FW-L T-2497 (note4)

App. R alternative 2-FW-LT-2477A shutdown:

2-FW-L T-2487 A NOTES: Additional instrumentation not relied on for Appendix R:

1. 1-RC-LT-1459 and 1-RC-LT-1460 provide additional indication of RCS pressurizer level.
2. 2-RC-LT-2459 and 2-RC-LT-2461 provide additional indication of RCS pressurizer level.
3. 1-RC-PT-1402 provides additional indication of RCS pressure. Additionally, there are 5 more RCS pressure transmitters on the pressurizer: 2 for control & 3 for protection.
4. 2-FW-LT-2477, 2-FW-LT-2487 and 2-FW-LT-2497A provide additional indication for steam generator level. Additionally. there are 3 more level transmitters on each steam generator (narrow range).

3 of 13

TABLE 2 INSTRUMENTATION CIRCUITS RELATING TO RADIANT ENERGY SHIELD APPLICATIONS NORTH ANNA UNIT 1 NORTH ANNA UNIT 2 A. RCS PRESSURE A. RCS PRESSURE INDICATION INDICATION App. R "primary" train:

1-RC-PT-1403 2-RC-PT-2402 (Note 1) 2-RC-PT-2403 (Note 2)

App. R alternative 1-RC-PT-1000 2-RC-PT-2000 shutdown:

A. RCS PRESSURIZER B. RCS PRESSURIZER LEVEL INDICATION LEVEL INDICATION App. R "primary" train:

1-RC-LT-1460 2-RC-LT-2461 (Note 3)

(Note 4)

App. R alternative 1-RC-LT-1000 2-RC-L T-2000 shutdown:

B. NEUTRON FLUX INDICATION (source ranQe)

App. R "primary" train:

1-NI-NE-32 (Note 5)

App. R alternative 1-NM-NFD-190 shutdown:

NOTES: Additional instrumentation not relied on for Appendix R:

1. 1-RC-PT-1402 provides additional indication of RCS pressure. Additionally, there are 5 more RCS pressure transmitters on the pressurizer: 2 for control & 3 for protection.
2. There are 5 more RCS pressure transmitters on the pressurizer: 2 for control & 3 for protection.
3. 1-RC-L T-1459 and 1-RC-L T-1461 provide additional indication of RCS pressurizer level.
4. 2-RC-LT-2459 and 2-RC-LT-2460 provide additional indication of RCS pressurizer level.
5. 1-NI-NE-31 and 1-NM-NFD-1270 provide additional source of source range neutron flux.

Additionally, there are several channels of intermediate & power ranQe neutron flux indication.

4 of 13

NRC Question (b)

The radiant energy heat shield designs used are constructed from 112 inch thick Thermo-Lag 330-1 conduit pre-shapes and panels. This material is combustible. The licensee in its submittal, stated that this material has a fire resistance rating of 20 minutes or more. The guidance of Branch Technical Position (BTP) 9.5-1, Section C.7.a.(1)b and of Generic Letter (GL) 86-10, Section 3.7., specifies a minimum fire resistance of 30 minutes and infers that a non-combustible material is being used as the radiant energy heat shield. Specifically, GL 86-10 refers to marinite board, a non-combustible material which, when tested as part of a fire barrier assembly, is capable of achieving.a 30-minute fire rating.

In addition, the guidance in GL 86-10 specifies that the radiant energy heat shields should be capable of protecting the required component or cabling during a fire from both convective and radiant heat energy.

Explain how a partial radiant energy heat shield, constructed from combustible materials and positioned between safe shutdown redundancies, is capable of performing its intended function under exposure fire conditions such as that which can be caused by an intervening combustible.

Virginia Power Response Thermo-Lag 330-1 fire barrier material is a water-based material which provides protection from a fire through a subliming process. The key components of Thermo-Lag 330-1 are subliming powder, resin, and chopped fiber (partially composed of fiberglass). When the minimum heat flux of 750 BTUs per pound or greater is directed towards the barrier, the subliming material boils off as the Thermo-Lag begins to change state. An endothermic process pyrolizes the resin (which holds the powder together) into a final state, known as the "char layer." The chopped fibers are an integral part of the char layer matrix. Underwriters Laboratories (UL), File No. R6076, Project No. 81 NK3238, tested Thermo-Lag 330-1 to ASTM E-84 to determine surface burning properties. This test reveale~Thermo-Lag 330-1 has a Flame Spread value of five (5), a Smoke Developed value of fifteen (15), and a Fuel Contributed value of zero (0).

Appendix R does not provide specific requirements for what constitutes a radiant energy shield. The guidelines in BTP APCSB 9.5-1, Section C.7.a(1)b., indicate that radiant energy shields should have a "fire barrier" fire resistance rating of one-half hour.

In Section 3.7.1 of GL 86-10, the NRC has stated any material with a one-half hour fire rating should be capable of performing the function of a radiant energy shield. This section goes on to state that non-fire-rated energy shields would also be acceptable if they have been demonstrated by a fire hazards analysis to provide protection against the anticipated hazard within the containment.

It is evident from the testing performed by the NRC, UL, and industry that Thermo-Lag 330-1 material does exhibit some combustible behavior at temperatures in excess of 5 of 13

1000 ° F or in the presence of large heat fluxes. It is not, however, a highly combustible material as substantiated by the UL test referenced above. Thermo-Lag installations in containment are such that there are negligible amounts of combustible material in the vicinity of the radiant energy shields. Since containment is a multi-level structure, heat and hot gasses from a fire would be directed upward and away from the radiant energy shields. The fire hazards analysis submitted with the exemptions shows the radiant energy shields are expected to provide protection against the anticipated hazard within the containment.

The radiant energy shields are not expected to be exposed to temperatures in excess of 1000 ° F or large heat fluxes. Therefore, the shields would be expected to perform their intended function under exposure fire conditions caused by the limited amounts of intervening combustibles found in containment.

Considering the factors described above, the absence of transient combustibles, and the limited number of ignition sources, it is extremely unlikely that a fire would start in any area that contains safe shutdown equipment and its associated cabling. If a fire were to start, it would not be expected to grow to any significant size or propagate to involve more than a small localized area.

When you combine the limited fixed combustibles near the radiant energy shields, the flame resistant nature of the cables (reference the response to Question (f) below), automatic detection (reference the response to Question (d) below), defense in depth, limited ignition sources, lack of transient combustibles, containment being a multi-level open structure, and that Thermo-Lag requires large heat fluxes or high temperatures to ignite, we conclude the radiant energy shields will perform their intended function.

NRC Question (c)

Provide the analysis performed which demonstrated that your radiant energy heat shields are capable of providing 20 minutes of fire resistance for the protected component.

In addition, provide the analysis which clearly demonstrates that the chemical composition of the Thermo-Lag material used to construct the installed radiant energy heat shields is equivalent to the chemical composition of the Thermo-Lag materials used to construct the fire barrier test specimens that established the 20-minute fire rating.

Virginia Power Response Radiant Energy Heat Shield Fire Resistance Analysis Texas Utilities (TU) instituted a fire endurance testing program to qualify its Thermo-Lag 330 electrical fire barrier systems (raceway protective envelopes) during the weeks of June 15, 1992 and June 22, 1992. These tests were witnessed by the NRC with the results described in NRC Bulletin 92-01. TU Electric's test program consisted of a 6 of 13

)-

series of. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> fire endurance tests (using ASTM E-119 Standard) on a variety of cable tray and conduit configurations.

The fire barrier installation on the conduit test configuration was performed in accordance with Thermo-Lag installation procedures and certified installers. On June 17, 1992, the first test was conducted. This test consisted of a junction box with a 3/4",

1 ", and 5" conduit entering and exiting the conduit box. The tested configuration used pre-formed %" thick Thermo-Lag 330 conduit shapes to provide a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> fire rating.

Throughout the test, the cable inside the conduit was monitored for low voltage circuit integrity, continuity, and temperature.

Throughout the test, none of the cables experienced a failure in circuit integrity.. At 60 minutes, the temperature on the inside..

cover of the junction box and inside the 3/4" and 1" conduits exceeded the 325

  • F cold side temperature criteria.

As a follow up to Bulletin 92-01, the test results were discussed with TU Comanche Peak Station on July 6, 1992. They indicated that at 30 minutes into the test the temperature inside the junction box and inside the 3/4" and 1" conduits was below 325 °F. Based on this information, the Thermo-Lag used as a radiant energy shield for conduit would be expected to satisfy the fire barrier criteria for a one-half hour fire rating.

On July 15, 1992, the National Institute of Standards and Technology (NIST) conducted small scale 1 and 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> fire endurance tests to determine the fire resistive properties of

% and 1 inch thick Thermo-lag pre-formed panels. The fire tests conducted by NIST were classified as small scale tests. The small scale tests are not considered definitive in that the tests were not full scale, and therefore the results are not used to qualify the fire rating of a material. The results of those tests were presented in NRG Information Notice 92-55, "Current Fire Endurance Test Results for Thermo-Lag Fire Barrier Material."

The tests consisted of a 31.5 inch square Thermo-Lag panel placed horizontally in a frame above a gas-fired furnace. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> test {%" thick panel) resulted in an average thermocouple reading on the unexposed side in excess of 325

  • F in approximately 22 minutes. The unexposed surface of the material reached an average temperature of 1206
  • F at 45 minutes.

On August 6, 1992, the NRG sponsored a second 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> fire endurance test on a Thermo-Lag 330 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> panel, which had stress skin on one side only. This panel was placed on the furnace with the stress skin towards the fire.

The stress skin was restrained by the furnace specimen support lip.

The average unexposed surface temperature of the specimen exceeded 325

  • F in 34 minutes. At 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, the maximum temperature of the unexposed surface was 458
  • F. However, the specimen was not burned through. The performance of the specimen in this test was superior to the specimen tested on July 15, 1992, for which the stress skin faced the unexposed side.

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.l -

In conclusion, the exemption requests state that when Thermo-Lag radiant energy shields are used as-a fire barrier they have a fire resistance rating typically of 20 minutes or more. This is conservatively based on the first NIST test described above (22 minute rating).

The TU tests described above are more representative of the conduit wrap and junction box enclosure configurations installed at North Anna and Surry, and TU's fire barrier tests show that the Y2" thick Thermo-Lag 330 raceway protective envelopes have a fire rating greater than 30 minutes. The NIST small scale test (indicating that Thermo-Lag panels have a fire rating of 22 minutes or 34 minutes) is not as reliable or as representative of installed conditions. Based on the TU tests, we conclude that the Surry and North Anna radiant energy shield conduit wraps will provide greater than 30 minutes of fire resistance for the protected component.

Thermo-Lag Chemical Composition Virginia Power reviewed the results of the NEI Generic Chemical Testing Program for Thermo-Lag material and the Company's records of purchased Thermo-Lag material for use at Surry and North Anna. Based on our review, we have determined that the results of the industry test program provide a firm basis to conclude that the chemical composition of the Thermo-Lag used at North Anna and Surry is consistent with that tested by NUCOM International, Inc. for the NEI effort. The consistent chemical test results from the broad population of Thermo-Lag represented validates the material should be considered equivalent regardless of the date of manufacture.

Based on the above referenced fire and chemical composition testing performed, Virginia Power finds that the high degree of chemical consistency exhibited adequately demonstrates that our Thermo-Lag materials should be considered equivalent to the Thermo-Lag materials discussed above. The chemical composition of the Thermo-Lag material used to construct the installed radiant energy shields is considered equivalent to the chemical composition of the Thermo-Lag materials used to construct the fire barrier test specimens that established the 20-minute fire rating.

NRC Question (d)

Provide a description of the automatic fire detection features provided in the areas where the radiant energy heat shields are installed.

Virginia Power Response:

Detection is provided in the areas where potential ignition sources exist or large concentrations of combustibles are present. Detection is typically not provided in the immediate vicinity of equipment or conduit protected by radiant energy shields since these areas in containment have no ignition sources or significant quantities of combustibles. North Anna also has detection provided for the RHR pumps which are 8 of 13

. separated by shields..The containment structures for both stations are provided with an automatic detection system that annunciates in the Control Room. There are three types of detectors in each containment: 1) continuous line type heat detectors, 2) smoke detectors and 3) heat detectors.

Detectors are provided in the following locations:

The majority of the smoke and heat detectors are located at the electrical penetration area of containment.

Line type heat detectors are provided for the Reactor Coolant pumps at both stations.

Duct-type smoke detectors are provided in the containment recirculation air system.

North Anna has heat detectors installed in the vicinity of the Residual Heat Removal pumps.

See Attachments 1 through 4 for a description of the radiant energy shields and detection found on each elevation of containment.

NRC Question (e)

On drawings, identify the physical location of the fire detection devices which are in close proximity of those redundant safe shutdown functions that are being protected by Thermo-Lag radiant energy shields. In addition, from the current level of fire detection intelligence inside the containment, describe. how* a fire in the area of these safe shutdown systems will be promptly identified and how its exact location will be communicated to the fire brigade. Describe, in a time-line sequence, the control room operators' response to a fire inside the containment, what actions they would take prior to alerting the fire brigade, the fire brigade's response, how the brigade would access the containment, locate the area of concern, and what actions would be taken to fight the fire.

Virginia Power Response Attachments 1 through 4 list the station drawings that identify the physical location of the fire detection devices and their location with respect to the redundant safe shutdown equip.ment that is being protected by Thermo-Lag radiant energy shields.

Figures 27-1 through 27-8 for Surry and Figures 37-1 through 37-8 for North Anna are also provided to show the relative location of the detectors and radiant energy shields.

Automatic heat detection is provided in the vicinity of the RHR pumps at North Anna and around the RC pumps for both stations.

Smoke detection is provided for the 9 of 13

containment recirculation air system at both stations. Smoke and heat detectors are provided for the electrical cables in the containment electrical penetration areas for both stations.

A fire in an area provided with an automatic detection system would initiate a signal that would be transmitted to the Control Room where the operators would be alerted and the station fire brigade notified. Fire detection will annunciate by zone location (i.e.,

cable penetration area, RC pumps, recirculation air system, or RHR pump area). The control room operators would initiate a procedure for a containment fire which could include shutting down the Unit in alarm.

Once the station fire alarm is sounded, the fire brigade would respond with appropriate fire fighting gear to the containment personnel hatch of the Unit in alarm. The fire brigade scene leader stays in radio contact with the control room throughout the event so that each is kept apprised of what is happening. Before entering containment, the manual isolation valves for the hose stations in containment would be opened. With the assistance of the Radiation Protection department, the fire brigade would proceed to enter containment and respond to the area associated with the alarm. Based on the results of their initial search, the fire brigade would initiate fire fighting as necessary using manual hoses and/or fire extinguishers. A time-line sequence describing the response to a fire in containment is provided below.

A fire in a location without detectors is expected to be small and short-lived due to a lack of combustibles or eventually detected by the duct-type smoke detectors in the recirculation air system.

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(Time in Minutes)

CONTAINMENT FIRE TIME LINE NORTH ANNA & SURRY POWER STATIONS 0 __

5 __ 10 __ 15 __ 20 __ 25 __ 30 __ 35 40 45 50 __ 55 __ 60 (0)

Detection in containment goes into alarm and annunciates in the Control Room (2) Control Room activates plant audible fire alarm and initiates the applicable procedures for a containment fire; operators will monitor control room instrumentation and initiate Site Emergency Plan, if necessary (5)

Fire brigade assembles at equipment locker, puts on turn out gear, and proceeds to the Radiological Controlled Area access control (9)

Fire brigade gets dosimetry and together with Radiation Protection personnel proceeds to containment personnel hatch *

(13) Fire brigade assembles at containment hatch and prepares to enter containment, opens manual valves controlling water to hose stations in containment (20)

Brigade enters containment and begins search based on location of alarm received in the control room 11 of 13 (35)

Brigade initiates fire fighting tactics; magnitude of fire will determine length of fire fighting effort

NRC Question (f)

To help mitigate the potential of fire spread along the trays, vertical and horizontal fire stops (Marinite Board and silicone foam) have been installed where the cable trays constitute a potential intervening combustible between redundant instrumentation components and cabling. The cabling at North Anna is not qualified per the IEEE*383 standard and the licensee has not conducted fire experiments which would validate expected plant-specific fire propagation in representative cable tray configurations.

Therefore, the fire propagation characteristics in the various horizontal tray configurations inside the containment are unknown. In order to substantiate the fire control features of the fire stop design, provide the technical bases and supporting experimental data which demonstrate that the flames of free burning cables in a horizontal cable tray will be adequately interrupted by the fire stops and that the flames will not bypass the fire stops and reach the cables above the fire stop.

Virginia Power Response Cable installed in the North Anna containments was specified to meet, as a minimum, the fire propagation test discussed below. Any cable construction that did not pass all of the qualification tests listed below was rejected and not permitted for use within the containment on safety related equipment.

a. A metallic test tray, approximately 8 ft. in length, should be arranged vertically, protected from drafts or winds, and loaded with one layer of cables allowing % of a cable diameter space between cables.
b. Crumpled burlap (24 x 24 in., 9 oz. /sq. yd) previously soaked with transformer insulating oil, was affixed approximately 12 in. above the lower cable ends and ignited and allowed to burn until the burlap igniter is consumed.
c. The cable sample was considered satisfactory if:

(1)

A self-sustaining or propagating fire did not result.

(2)

Electrical integrity was not lost in less than 5 minutes after ignition.

(3)

Excessive smoke did not appear from cable sample after burlap is consumed.

(4)

Hot drippings of insulation did not result.

This test is similar to the alternative flame source allowed in the IEEE-383 standard.

North Anna cable in containment is considered similar to IEEE-383 for flame resistance.

(Surry's cable is flame resistant as described in Exemption Request #27.)

The fire stop design is based on three separate fire tests. These tests provide the technical bases and supporting experimental data to demonstrate that the flames of 12 of 13

free burning cables in a horizontal cable tray will be adequately interrupted by the fire stops and that the flames will not bypass the fire stops and reach the cables on the other side of the fire stop.

The first two tests were conducted at North Anna Power Station on December 15 and 20, 1976 on horizontal cable trays. The December 15, 1976 test used a 3 in. x 30 in.

aluminum cable tray with a 40% cross sectional fill of control, power, and instrumentation cable. Cable types used were representative of those installed in the plant. The tray used cerafiber as damming material and was sealed with silicone foam.

The second test involved cable tray covers which consisted of a double layer of Marinite XL board separated by a 1 in. air space. The first test resulted in no passage of flame or gasses hot enough to ignite the cable on the unexposed side and the temperature on the unexposed side was not raised more than 250 ° F above its initial temperature. The second test showed a 1 % hour fire rating for the cable tray covers and the unexposed side of the tray cover remained intact throughout the test.

The third test was conducted by WYLE Laboratories on April 19, 1985, and documented in Report No. 17666-02, Rev. A. The test was conducted as part of a total analysis being performed for Duquesne Light Company's Beaver Valley Power Station, Unit 2.

The tests performed for horizontal cable trays (configurations 3 & 4) demonstrated the acceptability of solid and ventilated tray covers in preventing ignition in adjacent trays.

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Elevation, Sketch Elev. 291'-10" Fig. 37-1 Elev. 262'-1 O" Fig. 37-2 Elev. 241 '-0" Fig. 37-3 Elev. 231 '-6" (Partial elev.

only)

Fig. 37-4 Elev. 216'-11" Fig. 37-4 ATT NORTH ANNA PO Radiant Energy Shield Description

1. Protection for RCS Pressurizer Level Indication &

RCS Pressure Indication circuits:

A. Box around Fuel Building cable penetration at column 5 B. Wrap on conduit 1 CX933NB for 1-RC-L T-1000 &

1-RC-PT-1000 from Fuel Building penetration down through floor grating at column 5

1. Protection for RCS Pressurizer Level Indication &

RCS Pressure Indication circuits:

A. Wrap on conduit 1 CX933NB from elev. 291 '-10" to (and including) junction box adjacent to transmitter at column 9 B. Panel between transmitters 1-RC-L T-1000 &

1-RC-LT-1460 at column 9 None on this elevation

1. Protection for Neutron Flux Indication circuits: Wrap on conduit 1 CX903WA4 for 1-NI-NE-32 & 36 between columns 4 & 6
2. Protection for RHR:

Panel between RHR pump motors 1 A & 1 B at column 5 None on this elevation NT 1 STATION UNIT 1 Fire Detection Manual Hose Reference Connections Drawings None on this elevation Two; one each 11715-between FAR-201, columns 7 & 8 Sh. 1; and 14 & 15.

11715-FE-57A& B 19 detectors between columns 7 Four; one each 11715-

& 9:

at columns 7 FAR-201, and 9, and one Sh. 2 5 heat & 5 smoke at elev. 271 '-6" each between columns 14 & 15 11715-FE-2 heat & 3 smoke at elev. 278'-0" 51L,57C&

and 18 & 1.

2 heat & 2 smoke at elev. 290'-

D 6".

Continuous line type heat None on this 11715-detectors, one for each Reactor elevation FAR-201, Coolant Pump cubicle Sh.3 11715-FE-51M, 57E &

F 4 heat detectors in the vicinity of None on this 11715-the RHR pump motors elevation FAR-201, Sh. 4 3 smoke detectors for None on this 11715-containment recirculation air elevation FAR-201, system Sh.4 11715-FE-57G & H

Elevation, Radiant Energy Shield Description Fire Detection Manual Hose Reference Sketch Connections Drawing Elev. 291 '-1 O"

1. Protection for RCS Pressure Indication circuit:

None on this elevation Two; one at 11715-column 11 and FAR-202, Fig. 37-5 A. Box around Fuel Building cable penetration, column one between Sh. 1 13 columns 4 & 5 12050-FE-B. Wrap on conduit 2CX906NV for 2-RC-PT-2000 from Fuel Building penetration down through floor grating 57A & B at column 13 Elev. 262'-10"

1. Protection for RCS Pressure Indication circuit:

20 detectors between columns 9 Four; one each 11715-Fig. 37-6 Wrap on conduit 2CX906NV from elev. 291 '-10" to

& 11:

between FAR-202, columns 1 & 2, 6 Sh.2 column 1 5 heat & 6 smoke at elev. 271 '-6"

& 7, 8 & 9, and

2. Protection for RCS Pressurizer Level Indication 3 heat & 2 smoke at elev. 278'-0" 14 & 15.

12050-FE-51F, 57C circuit:

2 heat & 2 smoke at elev. 290'-6"

&D A. Panel between transmitters 2-RC-LT-2000 & 2-RC-LT-2461 at column 6 B. Wrap on conduit 2CX906NV for 2-RC-LT-2000 from (and including) junction box adjacent to the transmitter, to column 5 Elev. 241'-0" None on this elevation Continuous line type heat None on this 11715-Fig. 37-7 detectors, one for each Reactor elevation FAR-202, Coolant Pump cubicle Sh. 3 12050-FE-51F,57E&

F Elev. 231 '-6"

1. Protection for RHR:

4 heat detectors in the vicinity of None on this 11715-(Partial Elev.

Panel between RHR pump motors 1A & 1B at the RHR pumps elevation FAR-202, Sh. 4 only) column 1 Fig. 37-8 Elev. 216'-11" None on this elevation 3 smoke detectors for None on this 11715-Fig. 37-8 containment recirculation air elevation FAR-202, system Sh.4 12050-FE-57G &H

Elevation, Radiant Energy Shield Description Fire Detection Manual Hose Reference Sketch Connections Drawings Elev. 47'-4" None on this elevation None on this elevation Four - one each 11448-fig. 27-1 at columns 1, 7, FAR-201, 12, & 15 Sh. 1 11448-FE-46C& D Elev. 18'-4"

1. Protection for RCS Pressurizer Level Indication 25 Detectors between columns 7 Three - one 11448-Fig. 27-2 circuit:

&9:

each at columns FAR-201, 1 and 12, & one Sh.2 A. Panel between transmitters 1-RC-L T-1459A &

4 smoke & 3 heat at el. 45'-4" between 1-RC-L T-1461 at column 10 5 heat & 5 smoke at el. 34'-6" columns 14 & 15 11448-FE-46A & B, B. Wrap on conduit for 1-RC-L T-1459A from 4 heat & 4 smoke at el. 25'-8" 64HG transmitter to between columns 11 & 12 Elev. (-)3'-6"

1. Protection for RCS Pressure Indication circuit:

Continuous line type heat Three - one 11448-Fig. 27-3 A. Box around transmitter 1-RC-PT-1449 at column 9 detector around each RCS pump between FAR-201, at el. 16'-0" columns 11 &

Sh.3 B. Wrap on conduit for 1-RC-PT-1449 from transmitter 12, and one 11448-FE-to column 7 each at columns 18G 14 &18 Elev. (-)13'-0"

1. Protection for RHR:

None on this elevation None on this 11448-(Partial Elev.

Panel between RHR pump motors 1 A & 1 B elevation -

FAR-201, at (Accessible from Sh. 4 only) column 4 Elev. (-)3'-6")

Fig. 27-4 Elev. (-)27'-7" None on this elevation 3 smoke detectors for contain-Three - one 11448-.

Fig. 27-4 ment recirculation air system each at columns FAR-201, 5, 11, & 14 Sh.4 11448-FE-64HF

Elevation, Radiant Energy Shield Description Fire Detection Manual Hose Reference Sketch Connections Drawing Elev. 47'-4" None on this elevation None on this elevation Four - one each 11448-at column 4 &

FAR-202, Fig. 27-5 17, one each Sh. 1 between 11548-FE-columns 6 & 7, 10 & 11 46C& D Elev. 18'-4"

1. Protection for RCS Pressurizer Level Indication 25 Detectors between columns 9 Three - one 11448-Fig. 27-6 circuit:

& 11:

each at columns FAR-202, 4, 7, & 14 Sh.2 A. Box around transmitter 2-RC-L T-2459A at column 5 4 smoke & 4 heat at el. 45'-4" B. Wrap on conduit for 2-RC-LT-2459A from 11548-FE-4 heat & 5 smoke at el. 34'-6" 46A& B transmitter to between columns 4 & 5 4 heat & 4 smoke at el. 25'-8" 11448-FE-

2. Protection for Steam Generator Level Indication 64HM circuit:

A. Wrap on conduit for 2-FW-LT-2487A from floor grating at column 8 to column 11.

Elev. (-)3'-6"

1. Protection for Steam Generator Level Indication Continuous line type heat Three - one 11448-Fig. 27-7 circuit:

detector around each RC Pump each at columns FAR-202, at el. 16'-0" 4,9,&14 Sh. 3 A. Wrap on conduit for 2-FW-L T-2487 A from floor grating at column 9 up to elev. 18'-4" at column 8 11548-FE-18N1 Elev. (-)13'-0"

1. Protection for RHR:

None on this elevation None on this 11448-elevation FAR-202, (Partial Elev.

Panel between RHR pump motors 1A &18 at (Accessible from Sh. 4 only) column 1 El. (-)3' -6")

Fig. 27-8 Elev. (-)27'-7"

1. Protection for Steam Generator Level Indication 3 smoke detectors for contain-Three - one Fig. 27-8 circuit:

ment recirculation air system each at columns 11448-Fig. 27-8 2,7,&13 FAR-202, A. Box around transmitter 2-FW-L T-2487 A at column 9 Sh. 4 B. Wrap on conduit for transmitter 2-FW-L T-2487 A 11448-FE-from transmitter up to Elev. (-)3'-6" at column 9 64HL

\\

i'

,I 1

I I

q.

l

~\\ I r 'till'J,* '1 r-17 16 12 r*

---w""'"'

MANIPULATOR CRANE J*CR*5 8

Notes:

Ther-e ore no Thermo-Log opphcot1ons on this elevotion~

    • a I Coble Troy Coble Troy with Fire Stop UL.IL.I Verticol Coble Troys

~

Fire Hose Connection RADIANT ENERGY SHIELD EXEMPTION REQUEST 27 REACTOR CONTAINMENT -

EL. 45' 4'

SURRY POWER STATION UNIT 1 FIGURE 27-1

2 17 16

  • { ~

r:ir;;

~~~

p,:J

((jjrj i.

I CABLE FOO Lf-145q.,,.

FR'OHELMJ"-G" JO EL 47'*4" Notes:

1. Thermo-Log opphcot1ons on this elevot1on lNor"citf'10Noc\\':-~~',~7 for RCS PRESSURIZER LEVEL A. Pone! between tronsmitters 1-RC-LT-1459A

&,-RC-L T-1461 ot column 10.

8. Wrop on conduit for l-RC-LT-1459A from tronsm1 tter to between columns 11 & 12.
2. 25 smoke ond heot detectors ore ;nstolled between columns 7 &
  • 9 on 3 elevot1ons os shown on drowing ll448-FE-64HG.

Coble Troy

    • I**

Coble Troy with Fire Stop UUUU Verticol Coble Troys IC<J HR I Fire Hose Connection EB Detector (Heot or Smoke)

@ L T-1459A - PRESSURIZER LEVEL

@ L T-1461 - PRESSURIZER LEVEL

@ L T-1459

- PRESSURIZER LEVEL

@ L T-1460

- PRESSURIZER LEVEL

~

RCPC-4C -(COMMUNICATIONS ANTENNA!

RADIANT ENERGY SHIELD EXEMPTION REQUEST 27 REACTOR CONTAINMENT EL. 18' - 4' SURRY POWER STATION UNIT - 1 FIGURE 27 - 2 1

~----

16

'i

/,

I r -:

17 HOISTIHG SPACE Of'EN TO (L 1*127'-7' 2

3 8

Notes:

1. Thermo-Log opphcot1ons on this elevot1on fNorcir I0Noc\\';.~~ii~~ r or RCS PRESSURE A. Box oround tronsmitter l-RC-PT-1449 ot column 9.

B. Wrop on conduit for l-RC-PT-1449 from tr_onsm1 tter to column 7.

2. Continuous lirie ~pe heot detectors ore 1nstolled oround eoch RC fTump ot elev. 16'-0".

Coble Troy

    • I**

Coble Troy with Fire Stop UUUU

  • Verticol Coble Troys Fire Hose Conne'ct1on 1-RC-PT-1402

- RCS PRESSURE 1-RC-PT-1411)2. RCS PRESSURE (j) l-RC-PT-1449 RCS PRESSURE RADIANT ENERGY SHIELD EXEMPTION REQUEST 27 REACTOR CONTAINMENT EL. H3'-6' SURRY POWER STATION UNIT 1 FIGURE 27-3

} !

I*

IB r

DETACHED PLAN-EL. <->13'-0' Notes:

1. Thermo-Log opohcotlon on this elevot1on provide protection foi-RHR:

Ponel between RHR pump motors IA & 18 ot column 4.

2. 3 smoke detectors ore 1nstol led 1n the conto1nment rec1rcl.llot1on 01r system.

EB Smoke Detector IC<::1 HR I F u-e Hose Connection RADIANT ENERGY SHIELD EXEMPTION REQUEST REACTOR CONTAINMENT -

EL. (-l27'-7' SURRY POWER STATION UNIT 1 FIGURE 27 - 4 f l 27

I

,j I*

CABlE F~ LT-245'iA CABLE FOR LT*2487A 2

I.,

CA8l.E FOR LT-2460 Notes:

There ore no Thermo-Log opphcotions on this elevot1on Coble Troy

    • I** Coble Troy with Fire Stop UUU Verticol Coble Troy

~ Fire Hose Connection RADIANT ENERGY SHIELD EXEMPTION REQUEST 27 REACTOR CONTAINMENT EL. 47'-4' SURRY POWER STATION UNIT 2 FIGURE 27 - 5 f 1

i f I,

I~,~

15 Cl<<.£ FOi LT*2'77A

~.~:.!*IJ"*6" TO'------+-~fo/

cP,81..E FOSI Lf-2417 RADIAHT ENERGY SHIELD R£0UIR£0 ON C(),IOOlf lstE NOTE 21 CCIOJIT RISE TO Al'PRO)I. EL *.t'3* *9"

.~

Notes:

I. ~~~t~~~~~~ ?~f1Rc'?t~RESSURf£Hi l1ifv'tc1rNoFcirtSN circuit:

A. Box oround tronsm1 tter 2-RC-L T-245gA ot column 5.

B. ~~o~e~.7ei,;>ngifJm~t /&R~.L T-245gA from tronsm1 tter

2. Thermo-Log oppl1cot1ons on this elevot1on_Qrov1de protection for STEAM GENERATOR LEVEL INDICATION c1rcu1t:

Wrop on condu1 t for 2-FW-L T-2487A from floor grot1ng ot column 8 to column 11.

3. 25 Detectors (heot or smoke) ore 1nstolled between columns 9 & 11 ot three elevot1ons os shown on drowing ll548-FE-64-HM.

Coble Troy

.. *I*.

I Coble Troy with Fire Stop uuuu Vert1col Coble* Troy EB Smoke & Heot Detectors

!C<J HR I Fire Hose Connection

@ L T-2459A - PRESSURIZER LEVEL L T-2460 -

PRESSURIZER LEVEL

~ LT-z45g -

PRESSURIZER LEVEL L T-2461 -

PRESSURIZER LEVEL RADIANT ENERGY SHIELD EXEMPTION REQUEST 27 REACTOR CONTAINMENT -

EL. 18'*-.4" SURRY POWER STATION UNIT 2 FIGURE 27 - 6 i

1

I

1.

1*

CABl.E F~ LT 2477A ll" TO R.IB'-4" I r -:

2 Notes:

1. Thermo-Log opphcot1ons on this elevot1on lNotctf'10Noc\\';.~~ii~7 for STEAM GENERATOR LEVEL Wrop on conduit for 2-FW-L T-2487A from floor groting ot column 9 up to el. 18'-4" ot column a.
2. Continuous line type heot detectors o.-'.e instolled oround eoch RC Pump ot el. 16'-0'.

WU L.J L.J Coble Troy Coble Troy with Fire Stop Verticol Coble Troys Fire Hose Connection

@ L T-2477A - STEAM.GEN. LEVEL !LOOP Al

@ L T-2497 - STEAM GEN. LEVEL !LOOP Cl

@ L T-2497A - STEAM GEN. LEVEL !LOOP Cl

{§).L T-24 77 - STEAM GEN. LEVEL !LOOP Al -

@L T-2487 - STEAM GEN. LEVEL !LOOP Bl RADIANT ENERGY SHIELD EXEMPTION REQUEST 27 REACTOR CONTAINMENT EL. (-)3'-5" SURRY POWER STATION UNIT 2 FIGURE 27 - 7 I

/

I

.I 1

<a.i..

i**'l r.

DET~CHED. PLAN EL.Hl3'-0' Notes:

1. Thermo-Log opphcot1ons on this elevot1on provide fN811:8A°NoN Iic;cu~~:EAM GENERATOR LEVEL A.Box oround tronsmitter 2-FW-LT-2487A ot column CJ.

B. Wrop on conduit for tronsmi tter2-FW-L T-2487A from tronsm1tter up to El. (-)3'-6' ot column 'l.

2. Thermo-Log opphcotions on this elevot1on provide protection for RHR:

Pone! between RHR pump motors !A & 18 ot column 1.

3. 3 smoke detectors ore 1nstolled 1n the conto1nment rec1rculot1on Olt" system.

I C<::J HR j Fire Hose Connec t1ons Smoke Detectors 0

2-RH-P-IA - RHR PUMP 2-RH-P RHR PUMP G) L T-2487A - STEAM GEN. LEVEL !LOOP Bl RADIANT ENERGY SHIELD EXEMPTION.REQUEST 27 REACTOR CONTAINMENT EL. H27'-7' SURRY POWER STATION UNIT 2 FIGURE 27 - 8 L:1

1 t'.*i
,,.w 1~11

"""I I

I

CASlE FOR PT *RC-1000 ANO LT-RC-1000,HAVING RADIANT ENERGY SHIELD CABLE COATING ON ICX933NB FROM EL 262'*10". ISEE NOTE I.Bl FUEL BUILDING CABLE PENETRATION AREA:

PENE. NO. RCPC*IFI CABLE FOR EX*CORE NEUTRON FLUX MONITOR SIGNAL NFD*l90 FROM EL. 262'-0N RADIANT ENERGY SHIELD AROUND CABLE PENETRATION AREA

!SEE NOTE I.Al r

r, IH~

r P*-:1 I

14 Notes:

1. Thermo-Log opphcot1ons on this elevot1on frov1de r'}~~

0 i 1c?s /Rfs~&~lITfo1~~~\\~~R ct.;i~l~S\\ND CATION A. Box or-ound Fuel Building coble penetrot1on ot column 5.

B. Wi-op on condu1 t ICX'l33NB f o.- 1-RC-L T-1000 &

l-RC-PT-1000 from Fuel Bu1ld1ng peneti-ot1on down thi-ough flooi-gi-ot1ng ot column 5.

  • * * * *
  • Coble Troy UUUU Vert1col Coble Troy IC<l HR I Fire HOSe Connection

@ STATION RADIO SYSTEM ANTENNA I-CD-ANT-7 STATION BACK-UP RADIO SYSTEM ANTENNA 1-CO-ANT-8 RADIANT ENERGY SHIELD EXEMPTION REQUEST 37 REACTOR CONTAINMENT EL. 291' - 10' NORTH ANNA POWER STATION UNIT 1

  • FIGURE 37 - 1

NEUTRON' FLUX MONITOR SlGN'At.

tFD*l<l0 F'ROM EL.241'*8" fO EL.2ql'-10 I

I r "

ISEE NOTE 21 3

12 13 16 17 2

I Notes:

1. Ther-mo-Lag opphcot1ons on this elevot1on l(rov1de

~rr;~c~

1CS /R°fs~S~lfNEo1t~~1r~~R c7;:~,~.]ND CATION A. Wrap on condu1 t 1CX933NB from elev. 291'-10" to Land 1nclud1ng) June t1on box odjocent to transm1 tter at column 9.

B. Panel between tronsm1tters l-RC-LT-1000 &

1-RC-L T-1460 ot column 9,

2. 19 Detectors ar-e installed between columns ii 7t5 _'}E°-1sii. elevations as shown on drawing

..... Cable Tray

. *I**. Cable Tray wilh Fire Slop uuu Vertical Cable Tray

~ Fire Hose Conneclion EB Deleclor <Heal or Smoke)

@ PT-1000 - PRESSURIZER PRESSURE G) LT-1000 - PRESSURIZER LEVEL

@LT-1460 - PRESSURIZER LEVEL

@ LT-1459 - PRESSURIZER LEVEL

@ LT-1461 - PRESSURIZER LEVEL RADIANT ENERGY SHIELD EXEMPTION REQUEST 37 REACTOR CONTAINMENT EL. 262' - 10".

NORTH ANNA POWER ST AT ION UNIT 1

FIGURE 37 - 2 I

/I I

FROII EL. 216'*11~

TO EL.262'*1r 4

3 11 i

13 16 17 Notes:

1. Ther-e ore no TKet"mo-Log opphcot1ons on this elevot1on.
2. Continuous l 1ne type heot detectors ore instolled for eocn RC Pump.

LI...JUU Coble Troy Vert1col Coble Troy

~

PT-1402 -

RCS PRESSURE 0

PT-1403 -

RCS PRESSURE RADIANT ENERGY SHIELD EXEMPTION REQUEST 37 REACTOR CONTAINMENT - EL. 241' - 0' NORTH ANNA POWER STATION UNIT 1 FIGURE 37 - 3 I I

J 8

PART PLAN-EL.231'-6" Notes

1. Thermo-Log opphcot1ons on this elevot1on provide protection for NEUTRON FLUX INDICATION circuits:

Wrop on conduit ICX903WA4 for 1-NI-NE-32 & 36 between columns 4 & 6 until 20 ft. of hor1zontoI seporot1on is ocheived with NFD-190.

2, Thermo-Log opphcotions on this eievot1on provide protection for RHR:

Pone! between RHR pump motors IA & IB ot column 5.

3. Detectors 1nstolled on this elevot1on:

A. 4 heot dete~tors ore 1nstolled 1n the vicim ty of the RHR pumps.

B. 3 smoke detectors ore 1nstolled for the Conto1nment rec1rculot1on 01r system.

II I* :*

~. Detectors (heot or smoke)

(D 01-NM-NFD-190 EL. 231 -

NEUTRON FLUX MONITOR

@ 01-NM-NFD-1270 EL. 231 -

NEUTRON FLUX MONITOR

@ 01-NI-NE INTERMEDIATE RANGE NEUTRON DET.

@ 01-NI-NE SOURCE RANGE NEUTRON DET.

@ 0!-NI-NE SOURCE RANGE NEUTRON DET.

f I

e

  • r *,

4 3

I 12

~-t-lD -ff RS*E*OC -r:fi ~

~-E*IB l*Sl*TK*IC 14

~

COMPRE3SOR EQUIPMENT 16 17 RADIANT ENERGY SHIELD EXEMPTION REQUEST 37 REACTOR CONTAINMENT EL. 216'-ll' NORTH ANNA POWER STATION UNIT 1 FIGURE 37 -

4 I '

L':'I'

~,

~--- I t-'"ii 11'<1 I';.~~

~

1*,.,

2 16 10 11 14 15 FU£1. 9UlLOJNG Ct.Sl.E PENETRATION AREA IPEN.NO.RCPC-2F"II Notes:

1. Thermo-Log opphcot1ons on this elevot1on provide protect10n for RCS PRESSURE INDICATION circuit:

A. ~~ru;:~oY:i'.d Fuel Building coble penetrotion, B.Wrop on conduit 2CXg06NV for 2-RC-PT-2000 from Fuel Building f:>enetrotion down through floor grot_ing ot column 13.

11!1 ****

Coble Troy UUUU Vertiool Coble Troy Fire Hose Connection

@ STATION RADIO SYSTEM ANTENNA 2-CO-ANT-4

@ STATION BACK-UP RADIO SYSTEM ANTENNA 2-CO-ANT-5 RADIANT ENERGY SHIELD EXEMPTION REQUEST 37 REACTOR CONTAINMENT EL. 291' - 10' NORTH ANNA POWER STATION - UNIT 2 FIGURE 37 - 5

5 4

2

' i:-,.

I 16 CABLE FOR PT-2*02 tPEN,NO.*RCPC70*21 C2CX026ADI 15 I

Notes:

1* 1~~~~;Lg~o~~gi;~~tt"ar;.s R 0ts t~~silfR1ti'~DICATION c1rcu1t:

Wrop on conduit 2CX906NV from elev. 291'-10' to column I.

2. Thermo-Log opphcotions on this elevotion fNo{ttt'1cfNoc\\';.~~ii~ for RCS PRESSURIZER LEVEL A. Pone! between tronsm1tters 2-RC-L T-2000

& 2-RC-L T-2461 ot column 6.

B. Wrop on condu1 t 2CX906NV for 2-RC-L T-2000 from (ond 1nclud1ng) junction box odjocent to the tronsm1 tter, to. column 5.

3. 20 Detectors ore 1nstolled between colum~s (zi.t5J!F'E::51F~levot1ons, os shown on drowing Coble Troy Coble Troy with Fire Stop LIL.IL.I Verticol Coble Troy

[§]

Fire Hose Connection EB Detector (Heot or Smoke)

@ PT-2000 PRESSURIZER PRESSURE (J) LT-2000, PRESSURIZER LEVEL G) LT-2461, PRESSURIZER LEVEL

@ LT-245'l, PRESSURIZER LEVEL

@ L T-2460, PRESSURIZER LEVEL RADIANT ENERGY SHIELD EXEMPTION REQUEST 37 REACTOR CONTAINMENT - EL. 262' - 10' NORTH ANNA POWER STATION UNIT 2 FIGURE 37 - 6

I r '

F Notes:

1. There ore no Thermo-Log opphcot1ons on this elevot1on.
2. Continuous hne type heot detectors ore instolled for eoch RC pump.

Co~le Troy 1-111.. 11-1 Vert1col Coble Troy

@ PT-2403. RCS PRESS

@ PT-2402, RCS PRESS RADIANT ENERGY SHIELD EXEMPTION REQUEST 37 REACTOR CONTAINMENT - EL. 241' - 0' NORTH ANNA POWER STATION UNIT 2 FIGURE 37 - 7 r;.:~

f i r -:

~;,,: J 10 I

11 16 RADIANT ENERGY SHIELD REQ'O BETWEEN RHR PUMPS

---',,~

tSEE NOTE \\I Notes:

PART PLAN-EL. 231'-6"

1. Thermo-Log opphcot1on on this elevot1on provide protection for RHR:

Pone! between RHR pump motors IA & 18 ot column I.

2. Detection for this elevot1on:

A. 4 neot detectors ore instolled in the v1c1mty of the RHR pumps.

B. 3 smoke detectors ore 1nstolled 1n the Conto1nment rec1rculot1on 01r system.

El, Detector (heot or smoke)

(D NF0-290 NEUTRON FLUX MONITOR, EL. 231'

@ NF0-2270 NEUTRON FLUX MONITOR, EL. 231' RADIANT ENERGY SHIELD EXEMPTION REQUEST REACTOR CONTAINMENT - EL. 216'-11' NORTH ANNA POWER STATION UNIT 2

FIGURE 37 - 8 37

14r---f---'

16 12 PLATFORM EL 47'-4' REFUELING CAVITY CONTROL ROD DRIVE SHIELD

    • -*wREACTOR
  • MANIPULATOR CRANE 1-CR-5 EL. 48'-4' ft. FUEL TRANSFER CANAL 8

FUEL,BUILDING CABLE PENETRATION

<PENETRATION NO. RCPC-lFll Notes:

There are no Thermo-Lag *applications on this elevation.

Cable Tray

\\

Coble Troy with Fire Stop UUl:.J Vertical Cable Troys

_lc<1 HRI Fire Hose Connection 9704280200.... 0J RADIANT ENERGY SHIELD EXEMPTION REQUEST 27 REACTOR CONTAINMENT - EL. 45' 4"

SURRY POWER STATION UNIT 1 FIGURE 27-1

16 CABLE FOR LT-145'lA

!SEE NOTE 1.8>

~-----1:*

0 Ill FUEL TRANSFER CAN,iL 8

INCORE INSTRUMENTATION EDUIP

& DRIVE ASSEMBLIES CABLE FOR LT-145'lA FROM EL H3'-6" TO EL 47'-4" Notes:

1. Thermo-Lag applications on this elevation l,)rov1de protection for RCS PRESSURIZER LEVEL INDICATION c1rcu1 t:

A. Panel between transmitters 1-RC-LT-1459A

& 1-RC-L T-1461 at column 10.

B.Wrap on conduit for 1-RC-LT-1459A from transm1 tter to between columns 11 & 12.

2. 25 smoke and heot detectors ore installed between columns 7 & 9 on 3 elevot1ons os shown on drawing 11448-FE-64HG.

Cable Tray

"*I*.

Cable Tray with Fire Stop f..lUUU Vertical Cable Trays IC<! HR I Fire Hose Connection Detector (Heat or Smoke)

@ L T-1459A - PRESSURIZER LEVEL

@ L T-1461 - PRESSURIZER LEVEL

@ L T-1459

- PRESSURIZER LEVEL

@ L T-1460

- PRESSURIZER LEVEL

@ RCPC-4C -CCOMMUNICATIONS ANTENNA>

RADIANT ENERGY SHIELD EXEMPTION REQUEST 27 REACTOR CONTAINMENT EL. 18' -

4 11 SURRY POWER STATION UNIT -

1 FIGURE 27 -

2

..--:-*-"--"'---------------------------------------------------------------------------------------------------------;,--t*,

17 16 INSTRUMENT PIT 12 HOISTING SPACE OPEN TO EL 1*>27'-7'

!SEE DETACHED PLAN, FIG.27*4>

3 8

-CABLE FOR PT*l44q TO EL 18'*4' CABLE FOR LT*l45qA TO EL 18'-4' Notes:

1. Thermo-Log opplicotions on this elevotion

[=>rovide protection for RCS PRESSURE lNDICA TIUN circuit:

A. Box around transmitter 1-RC-PT-1449 at column 9.

RADIANT ENERGY SHIELD AROUND CONDUIT I!. XMTR for I -RC-PT-l44q

!SEE NOTE I.Bl B. Wrap on conduit for 1-RC-PT-1449 from transmitter to column 7.

2. Continuous line 1Ype heat detectors are installed around each RC P-ump at elev. 16'-0".
          • Cable Tray
    • I* II Coble Troy with Fire Stop UUUL.J Vertical Cable Trays jC<l HR I Fire Hose Connection 1-RC-PT-1402 RCS PRESSURE 1-RC-PT-1402. RCS PRESSURE (I) 1-RC-PT -1449 RCS PRESSURE RADIANT ENERGY SHIELD EXEMPTION REQUEST REACTOR CONTAINMENT EL. (-)3'-6 11 SURRY POWER STATION UNIT 1 FIGURE 27-3 27

INSTRUMENT PIT VALVE PIT ACCESS SHAFT CABLE FOR PT-1402 STORAGE AREA

!0

© 3

CONT ON PLAN PLENUM DETACHED PLAN-EL. <->13'-0' Notes:

1. Thermo-Lag apohcation on this elevation provide protection for RHR:

Panel between RHR pump motors

!A & 1B at column 4.

2. 3 smoke detectors are installed in the containment recirculation air system.

E9 Smoke Detector

!C<i HR I F1t*e Hose Connection RADIANT ENERGY SHIELD EXEMPTION REQUEST 27 REACTOR CONTAINMENT EL. (-)27'-7' 1

SURRY POWER STATION UNIT 1 FIGURE 27 - 4 0 -

.-~-~~*--='r---------------------------------------------------'----------------------------------------------------~.-.--*.

~

CABLE FOR LT*245'1A CABLE FOR LT-2487A---~:::t==1~~~--LL-------------_j CONTROL ROD DRIVE SHIELD IOLOGICAL SH ELD WALL ITYPJ 0

CABLE FOR LT-2460 Notes:

There are no Thermo-Lag applications on this elevation

          • Cable Tray
    • I** Coble Troy with Fire Stop UUU Verticol Coble Troy lc<1 HR I Fire Hose Connection RADIANT ENERGY SHIELD EXEMPTION REQUEST 27 REACTOR CONTAINMENT EL. 47'-4" SURRY POWER STATION UNIT 2 FIGURE 27 - 5

CABLE FOR LT-2477A FROM EL. 1-13' -6" TO EL. 47' -4" RAOIANT ENERGY SHIELD REQUIRED ON CONDUIT

!SEE NOTE 2>

CONDUIT RISE TO APPROX. EL. 45' -0" 3

SEAL TABLE Notes:

1. Thermo-Lag applications on this elevation provide protection for RCS PRESSURIZER LEVEL INDICATION circuit:

A. Box around tronsmi tter 2-RC-L T-245gA ot column 5.

8. Wrap on conduit for 2-RC-L T-245gA from transmitter to between columns 4 & 5.
2. Thermo-Lag applications on this elevation P-rovide protection for STEAM GENERATOR LEVEL INDICATION circuit:

Wrap on conduit for 2-FW-LT-2487A from floor grating at column 8 to column 11.

3. 25 Detectors Cheat or smoke) are installed between columns g & 11 at three elevations as shown on drawing 11548-FE-64-HM.
        • u*
    • *In* 1 uuuu E9

!C<J HR I Cable Tray Cable Tray with Fire Stop Vertical Cable Tray Smoke & Heat Detectors Fire Hose Connection

@ L T-245gA - PRESSURIZER LEVEL

~ LT-2460 -

PRESSURIZER LEVEL

~ LT-245g -

PRESSURIZER LEVEL L T-2461 -

PRESSURIZER LEVEL RADIANT ENERGY SHIELD EXEMPTION REQUEST REACTOR CONTAINMENT EL. 18'-4 11 SURRY POWER STATION UNIT 2 27 r--,.

L___:~..:.....:..:.._ ___________________________

---t;J!~~~~~~~-~~

_--=__,F,-IG_UHR'--E--2-7_-_6 ______,~_'_:J.. ~

CABLE FOR LT 2477A UP TO EL. 18'*4" 15

~

Fl.EL TRANSFER CANAL 10 FROM EL 1*127'*7" OPEN TO ELl*ll:t-0"

!SEE DETACHED PLAN.

FIG, 27-81 CABLE FOR LT* 24'17 TO EL. 18' *4" Notes:

1. Thermo-Lag applications on this elevation l:)rov1de protection for STEAM GENERATOR LEVEL INOICA TION circuit:

Wrap on conduit for 2-FW-LT-2487A from floor grating at column CJ up to el. 18'-4" at column 8.

2. Continuous line type heat detectors are installed around each RC Pump at el. 16'-0".
        • 'II* I UULJU Cable Tray Cable Tray with Fire Stop Vertical Cable Trays Fire Hose Connection

@ L T-2477A - STEAM GEN. LEVEL (LOOP A>

©) L T-2497 - STEAM GEN. LEVEL <LOOP Cl

@ L T-24g7A - STEAM GEN. LEVEL <LOOP Cl

@ LT-2477 - STEAM GEN. LEVEL <LOOP Al

@ LT -2487 - STEAM GEN. LEVEL <LOOP B>

RADIANT ENERGY SHIELD EXEMPTION REQUEST 27 REACTOR CONTAINMENT EL. (-)3'-6 11 SURRY POWER STATION UNIT 2 FIGURE 27 - 7 4280

10 15 CABLE Fa:! L T*2487A TO EL. 1-13'*6" 3

3 PI.ENIJH DETACHED PLAN EL.<->13'-0" Notes:

1. Thermo-Log opphcotions on this elevotion provide protection for STEAM GENERATOR LEVEL INDICATION c1rcui t:

A.Box around transmitter 2-FW-LT-2487A at column 9.

8. Wrap on conduit for transmitter2-FW-LT-2487A from transmi.tter up to El. (-)3'-6 1 at column 9.
2. Thermo-Lag applications on this elevation provide protection for RHR:

Panel between RHR pump motors lA & 18 at column 1.

3. 3 smoke detectors are installed in the containment recirculotion air system.

I C

RADIANT ENERGY SHIELD EXEMPTION REQUEST REACTOR CONTAINMENT EL. (-)27'-7

SURRY POWER STATION UNIT 2 FIGURE 27 - 8 27

..--J~.. !:...........-"---------------------------------~-------------------------------~*,-;-*~._

CABLE FOR PT -RC-1000 AND LT-RC-1000,HAVING RADIANT ENERGY SHIELD CABLE COATING ON ICX933NB FROM EL 262'-10'. !SEE NOTE !.Bl FUEL BUILDING CABLE PENETRATION AREA:

PENE. NO. RCPC-!Fl CABLE FOR EX-CORE NEUTRON FLUX MONITOR SIGNAL NFD-190 FROM EL. 262'-0" RADIANT ENERGY SHIELD AROUND CABLE PENETRATION AREA CSEE NOTE I.Al I

2 16 t----f---i14 1-FP-284 Notes:

1. Thermo-Lag applications on this elevation provide J?rotection for RCS PRESSURIZER LEVEL INDICATION

& for RCS PRESSURE INDICATION circuits:

A. Box around Fuel Building cable penetration at column 5.

B. Wrap on conduit 1CX933NB for 1-RC-L T-1000 &

1-RC-PT-1000 from Fuel Building penetration down through floor grating at column 5.

  • * * * *
  • Cable Tray I.J UUU Ver-t1cal Cable T ra1:J JC<J HR I Fire Hose Connection STATION RADIO SYSTEM ANTENNA 1-CO-ANT - 7 STATION BACK-UP RADIO SYSTEM ANTENNA 1-CO-ANT-8 RADIANT ENERGY SHIELD EXEMPTION REQUEST 37 REACTOR CONTAINMENT EL. 291' - 10 11 NORTH ANNA POWER STATION UNIT 1

FIGURE 37 - 1 4280200 -09

NEUTRON FLUX MONITOR S!GNA~

NFD-1q0 FROM EL. 241'*0' TO EL. 2q1*-10 CSEE NOTE 21 4

3 l*NS*P-IA

~

V 12 17 I

Notes:

1. Thermo-Lag applications on this elevation provide P-rotection for RCS PRESSURIZER LEVEL INDlCATION

& for RCS PRESSURE INDICATION circuits:

A. Wrap on conduit 1CX933NB from elev. 291'-10" to (and including) junction box adjacent to transmitter at column 9.

B. Panel between transmitters 1-RC-LT-1000 &

1-RC-LT-1460 at column 9.

2. 19 Detectors are installed between columns 7 & 9 at 3 elevations as shown on drawing 11715-FE -5llo Cable Tray
  • *I* 11 Cable Tray with Fire Stop uuu IC<JI Vertical Cable Tray Fire Hose Connection El, Detector <Heat or Smoke)

@PT-1000 - PRESSURIZER PRESSURE CT) L T-1000 - PRESSURIZER LEVEL

@L T-1460 - PRESSURIZER LEVEL

@ L T-1459 - PRESSURIZER LEVEL

@ L T-1461 - PRESSURIZER LEVEL RADIANT ENERGY SHIELD EXEMPTION REQUEST 37 REACTOR CONTAINMENT EL. 262' - 10 11 NORTH ANNA POWER STATION UNIT 1

FIGURE 37 - 2

,, -~

~*"---'i---,--,--------------------------------------------------------------------------------------------------------__,\\.

FROM EL. 216'-ll" TO EL. 262'-IO" CABLE FOR PT-1403 NEUTRON FLUX CABLE NFD-1270 NEUTRON FLUX MONITOR SIGNAL NFD-190 FROM EL. 231'-6" T EL. 262'-IO EL 251"-ll" 8

16 3

1'7 1

Notes:

1. There are no Thermo-Lag applications on this elevation.
2. Continuous line type heat detectors are installed for eacn RC Pump.

Cable Tray LLIUU Vertical Cable Tray PT-1402 RCS PRESSURE

@ PT-1403 - RCS PRESSURE RADIANT ENERGY SHIELD EXEMPTION REQUEST REACTOR CONTAINMENT - EL.241' - 0" NORTH ANNA POWER STATION UNIT 1 FIGURE 37 - 3 37

8 NEUTRON l'LUX CABLE NFD-1270 N PLAN VIEW) j NEUTRON FLUX COl*Nl*NE-32138>

RADIANT ENERGY SHIELD CABLE COATING ON CONDUIT lCX903WA4 (SEE NOTE II NEUTRON FLUX CABLE NFD-190 UP TO EL. 241'*0" CABLE (011 PLAN VIEW>

PART PLAN-EL.231'-6" 3

Notes

1. Thermo-Lag applications on this elevation provide protection for NEUTRON FLUX INDICATION circuits:

Wrap on conduit 1CX903WA4 for 1-NI-NE-32 & 36 between columns 4 & 6 until 20 ft. of horizontal separation is acheived with NFD-190.

2. Thermo-Lag applications on this elevation provide protection for RHR:

Panel between RHR pump motors lA & 1B at column 5.

3. Detectors
  • installed on this elevation:

A. 4 heat detectors are installed in the vicinity of the RHR pumps.

B. 3 smoke detectors are installed for the Containment rec1rculat1on air system.

EB Detectors (heat or smoke)

(D 01-NM-NFD-190 EL. 231 -

NEUTRON FLUX MONITOR 01-NM-NFD-1270 EL. 231 -

NEUTRON FLUX MONITOR

@ 01-NI-NE INTERMEDIATE RANGE NEUTRON DET.

@ 01-NI-NE SOURCE RANGE NEUTRON DET.

@ 01-NI-NE SOURCE RANGE NEUTRON DET.

~:~

3 1-DG-P*IA 1-DG-P-IB

~

CD COMPRESSOR EQUIPMENT 16 14 RADIANT ENERGY SHIELD EXEMPTION REQUEST REACTOR CONTAINMENT EL. 216'-11 11 NORTH ANNA POWER STATION UNIT 1 FIGURE 37 - 4 37

6 3

SPIRAL 0 STAIRSY 10 15 CABLE FOR PT-RC-2000 &. L T-RC-2000 I 2CX906NV> WITH RADIANT ENERGY SHIELD CABLE COATING !SEE NOTE I.Bl FUEL BUILDING CABLE PENETRATION AREA

!PEN. NO. RCPC-2FU RADIANT ENERGY SHIELO AROUND PENETRATION AREA

!SEE NOTE I.Al FROM EL. 262'-10". CABLE FOR PT-2403 I 2TX018Yl Notes:

1. Thermo-Log opphcotions on this elevotion provide protection for RCS PRESSURE INDICATION c1rcui t:

A. Box around Fuel Building coble penetrotion, column 13.

B. Wrap on conduit 2CX906NV for 2-RC-PT-2000 from Fuel Building P-enetration down through floor grating at column 13.

Cable Tray L.JL.JL.JU Vertical Cable Tray Fire Hose Connection

@ STATION RADIO SYSTEM ANTENNA 2-CO-ANT-4

~ STATION BACK-UP RADIO SYSTEM ANTENNA 2-CO-ANT-5 RADIANT ENERGY SHIELD EXEMPTION REQUEST 37 9

REACTOR CONTAINMENT EL. 291' - 10" NORTH ANNA POWER STATION - UNIT 2 FIGURE 37 - 5

  • 1 '

6 RAO!ANT ENERGY SHLD CA COATING ON CONDUIT ISEE NOTE 2.8>

4 3

JB-2189-2 8

2 PLATE EL 270'-5" SPIRAL STAIRS 8

CABLE r.oR PT-2402 IPEN. NO,- RCPC 70-2>

I 2CX026RO>

0)

CABLE FOR PT-2403 IPEN, NO.- RCPC 15E-2>

( 2T 023Y>

FUEL TRANSFER CANAL 16 RADIANT ENERGY SHIELD CABLE COATING ON CONDUIT ISEE NOTE I>

Notes:

1. Thermo-Lag applications on this elevation provide protection for RCS PRESSURE INDICATION circuit:

Wrap on conduit 2CX906NV from elevo 291'-10' to column 1.

2. Thermo-Lag applications on this elevation provide protection for RCS PRESSURIZER LEVEL INDICA TIUN circuit:

A. Panel between transmitters 2-RC-L T -2000

& 2-RC-L T -2461 at column 6.

B. Wrap on conduit 2CX906NV for 2-RC-LT-2000 from (and including) junct10n box adjacent to the transmitter, to column 5.

3. 20 Detectors are installed between columns 9 & 11 at 3 elevations, as shown on drawing 12050-FE -51F.

Cable Tray

    • I-*

Cable Tray with Fire Stop L..lL..11..1 Ver ti col Coble Troy Fire Hose Connection Detector (Heat or Smoke)

@ PT-2000 PRESSURIZER PRESSURE (J) LT-2000,PRESSURIZER LEVEL

~ LT-2461,PRESSURIZER LEVEL

~LT-2459,PRESSURIZER LEVEL

~ LT-2460,PRESSURIZER LEVEL

,-,*!...*-*:.,-,-;_,->-=--,,__ __________________________________________________ *----------------------------------------------------~.

4 3

7 2

<SEE PART PLAN ELEV. 231'-6",

FIG. 37-8)

OPEN TO EL 231'*0" 10 GRATING EL 239'-0" 11 15

~** :*

16 2

I 97 AYID@ ~Wt;;illiw.iflJJ~@ @ITTJ ffe'.lp~li1i!!.iW'@ C~!i'(U Notes:

1. There are no Thermo-Lag applications on this elevation.
2. Continuous hne type heat detectors are installed for each RC pump.
        • ll Coble Troy Vertical Cable Tray

@PT-2403, RCS PRESS

@ PT-2402, RCS PRESS RADIANT ENERGY SHIELD EXEMPTION REQUEST REACTOR CONTAINMENT - EL. 241' - 0" NORTH ANNA POWER STATION UNIT 2 4 2 8 0 0 0 FIGURE 7 - 7 37

(

r--......... *=-'....:~:;.* ----------------------------------------------------------------------------------------------------------,_-.,;

0 0

0 6

2-RS-P-lB

~,..,,_,

8 STAIRS

<SEE NOTE 2.Bl INCORE INSTRUMENT TUNNEL 2-HV-E*2B 2-IA*D-28 "Fl ~2-IA*D*2A 2*1A*C*2B -jg_j l_Q-2*IA*C*2A CONDUIT FOR NEUTRON FLUX MONITORING DOWN TO IN-CORE INSTRUMENT TUNNEL

<SEE EXEMPTION REQUEST 2>

3 RADIANT ENERGY SHIELD REQ'D BETWEEN RHR PUMPS

<SEE NOTE ll Notes:

1. Thermo-Lag protection PART PLAN-EL. 231'-6" Panel between RHR pump motors lA & 1B at column 1.
2. Detection for this elevation:

A. 4 heat detectors are installed in the v1cini ty of the RHR pumps.

B.3 smoke detectors are installed in the Containment recirculation air system.

EB Detector Cheat or smoke)

Q) NFD-290 NEUTRON FLUX MONITOR, EL. 231'

@ NFD-2270 NEUTRON FLUX MONITOR, EL. 231' RADIANT ENERGY SHIELD EXEMPTION REQUEST REACTOR CONTAINMENT - EL. 216'-11" NORTH ANNA POWER STATION UNIT 2

FIGURE 37 - 8 37

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