ML20206P415

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Forwards Summary of Insulation on Piping & Equipment Inside Containments,Per Sser 2 & Util
ML20206P415
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 06/19/1986
From: Tucker H
DUKE POWER CO.
To: Harold Denton, Youngblood B
Office of Nuclear Reactor Regulation
References
NUDOCS 8607020120
Download: ML20206P415 (6)


Text

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DUKE Powna GOMPANY P.O. Box 33189 CHARLOTTE, N.C. 28242 HAL B. TUCKER tutzessown (704) 373-4531 vera reasement June 19, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Constission Washington, D. C.

20555 Attention:

Mr. B. J. Youngblood, Project Director PWR Project Directorate No. 4 Ret Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414

Dear Sir:

As discussed in the Catawba SER, Supplement 2, Section 6.3.4.1 and in our letter dated January 14, 1983, a survey of insulation in containment by type and location was to have been provided to you prior to startup from the first refueling outage for Unit 1.

We have completed this survey for Catawba Unit I and Unit 2.

A summary of the insulation on piping and equipment inside Catawba Unit 1 and Unit 2 Containments is attached. This submittal fulfills our commitment with respect to the issue of potential sump debris from insulation inside containment.

Very truly yours, K

Hal B. Tucker LTP sib Attachments xct Dr. J. Nelson Grace, Regional Administrator U. S. Nuclear Regulatory Commission Region Il 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 01 NRC Resident Inspector 0

Catawba Nuclear Station

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8607020120 060619 PDR ADOCK 05000413 E

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INSULATION ON PIPING AND EQUIPMENT INSIDE CATAWBA UNIT 1 CONTAINMENT I.

The following piping systess are insulated inside Unit I containment:

Steam Generator Blowdown Recycle Stean-BB Auxiliary Feedwater System-CA Feedwater System-CF Reactor Coolant System-NC Residual Heat Removal System-ND Ice Condenser Refrigeration System-NF Safety Injection System-NI Chemical & Volume Control System-NV Main Steam System-SM Steam Generator Level Instrumentation Lines-CFI The NF system is insulated with conventional insulation, all the others are insulated with reflective insulation.

Reflective insulation: All raflective insulation is mirror insulation, manufactured by Diamond Power Specialty Co., an all stainless steel insulation.

Insulation units are buckled together with spring locked buckle fasteners.

Drawings showing the mirror insulated piping are identified on Attachment 1.

Each system package contains a CN 1690-MI series drawing which is an insulation piping composite drawing for that system. This drawing shows piping location as it runs through containment. Each package also contains insulation drawings and flow diagrams, marked to show insulated lines. The exception are the generator level lines (CFI). This is not an actual mechanical system but is instrumentation lines (Tubing) and were field routed so the only drawings available are the insulation drawings, which are attached. These lines run down the crane wall in each of the 4 ST generator cavities from Elevation 617'5" to about Elevation 588'.

Conventional Insulation: Refrigerant Lines of the NF System are insulated with either Owens-Corning Fiberglass Pipe Insulation or with Armaflex II by Armstrong World Industries. The header and piping to the floor beam coolers, along with all heat traced lines are insulated with fiberglass, covered with a.01" thick stainless jacket. The jseket is banded on with 1/2" stainless steel bands on 12" centers. Piping to the air handling units is insulated with armaflex. The armaflex is jacketed the same way as the fiberglass.

All conventionally insulated pipe is located in the Ice Condenser or in upper containment, there is none in lower containment.

_2-II.

The following equipment is insulated inside Unit I containment.

Reactor Vessel-Mirror Insulation & Transco Insulation Steam Generators-Mirror Insulation Reactor Coolant Pumps-Mirror Insulation Regenerative HX-Mirror Insulation Excess Letdown HK-Mirror Insulation Pressurizer-Mirror Insulation Glycol Expansion Tank-1 1/2" Fiberglass Board The reactor vessel itself is insulated with mirror insulation, the reactor vessel head is insulated with Transco reflective insulation manufactured by Transco Inc. Transco is also an all stainless steel insulation similar to mirror. This insulation was supplied by Westinghouse as part of the NSSS contract.

The glycol expansion tank is insulated with Owens-Corning fiberglass covered with a stainless steel jacket. This tank is located on top of the ice condenser in upper containment.

INSULATION ON PIPING AND EQUIPMENT INSIDE CATAWBA UNIT 2 CONTAINMENT Insulation type and location for piping and equipment in Unit 2 containment are the same as listed for Unit I with one exception. The pressurizer surge line (NC System) on Unit 2 is insulated with fiberglass blanket insulation, whereas reflective insulation is used on Unit 1.

Drawings identified for Unit 1 are applicable to Unit 2, in that insulation type is identical and general building location is the same. Some minor variations in pipe routing may occur on small bore piping. (Less than 6")

Drawing CN2690-MI-203 SHT 2 shows the Unit 2 pressurizer surge line. This line is insulated with fiberglass blanket insulation manufactured by Insulation Technology Inc., Niles, Ill. The blankets are made of Knauf Fiberglass Blankets sewn inside of a fiberglass cloth. Blankets are attached to pipes with stainless steel velcro fasteners.

Blankets are covered with 22 gauge stainless steel jacket. The jackets are fastened with spring locked buckle fasteners identical to those used on the reflective insulation.

Insulation Technology Inc. has supplied Duke Power and the NRC with test information pertaining to containment emergency sump performance.

(See Attachment 2.)

ATTACHMENT 1 LIST OF PROVIDED DRAWINGS CN-1041-1 CN-1554-1.0 CN-1041-5 CN-1554-1.5 CN-1041-8 CN-1558-2.0 CNN-1201.01-0011, SHEET 1 CN-1558-2.1 CNN-1206.13-0019 SHEET 1 CN-1558-2.2 CNN-1206.13-0019, SHEET 1 CN-1558-2,3 CNN-1260.13-0036, SHEET 1 CN-1558-2.4 CNN-1206.13-0039, SEEETS 1-8 CN-1558-2.5 CNN-1260.13-0040 SHEETS 1 & 2 CN-1558-2.6 CNN-1260.13-0042, SHEETS 1-8 CN-1558-2.7 CNM-1260.13-0043, SHEET 1 CN-1558-2.8 CNN-1260.13-0044, SHEETS 1 & 2 CN-1558-2.9 CNN-1260.13-0045, SHEET 1 CN-1561-1.0 CNN-1260.13-0046, SHEET 1 CN-1561-1.1 CNN-1260.13-0047, SHEETS 1-11 CN-1562-1.0 CNN-1260.13-0048, SHEETS 1-6 CN-1562-1.1 CNN-1260.13-0049, SHEETS 1 & 2 CN-1562-1.2 CNN-1260.13-0050, SHEET 1 CN-1565-2.6 CNM-1260.13-0051, SHEETS 1-10 CN-1580-1.0 CNN-1260.13-0052, SHEETS 1-4 CN-1591-1.1 CNM-1260.13-0053, CHEETS 1-4 CN-1592-1.1 CNN-1260.13-0054, SHEETS 1-5 CN-1593-1.0 CNM-1260.13-0055, SHEETS 1-14 CN-1591-NF-001 THRU CN-1491-NF-0020 CNN-1260.13-0056, SHEETS 1-6 CN-1491-NF-0021 THRU CN-1491-NF-0032 CNN-1260.13-0057, SHEETS 1-9 CN-1491-NF-0035 THRU CN-1491-NF-0060 CNM-1260.13-0058, SHEETS 1-4 CN-1491-NF-081 THRU CN-1491-NF-137 CNM-1260.13-0059, SHEETS 1 & 2 CN-1491-NF-139 CNN-1260.13-0060, SHEETS 1-3 CN-1491-NF-146 CNM-1260.13-0061, SHEETS 1 & 2 CN-1491-NF-147 CNN-1260.13-0062, SHEETS 1 & 2 CN-1491-NF-173 THRU CN-1491-NF-196 CNN-1260.13-0063, SHEETS 1-32 CN-1690-MI-201, SHEET 1-3 CNN-1260.13-0064, SHEETS 1-9 CN-1690-MI-203, SHEET 1-5 CNM-1260.13-0065 SHEETS 1-18 CN-1690-MI-204, SHEETS 1 & 2 CNN-1260.13-0066, SHEETS 1-5 CN-1690-MI-205 CNM-1260.13-0067, SHEETS 1-6 CN-1690-MI-206 CNN-1260.13-0068, SHRETS 1-8 CN-1690-MI-207, SHEETS 1 & 2 CNM-1260.13-0069, SHEETS 1-17 CN-1690-MI-208 CNM-1260.13-0070, SHEETS 1-7 CNM-1260.13-0071, SHEETS 1-5 CNN-1260.13-0072, SHEETS 1-3 CNM-1260.13-0073, SHEETS 1-27 CNM-1260.13-0074, SHEETS 1 & 2 CNM-1260.13-0075, SHEETS 1-5 CNN-1260.13-0076, SHEETS 1-4 CNM-1260.13-0077, SHEET 1 CNN-1260.13-0078, SHEETS 1-4 CN-2690-MI-203, SHEET 2 CN-1553-1.0 CN-1553-1.1 CN-1553-1.2

ATTACHMENT 2 f

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e yw UNITED STATES NUCLEAR REGULATORY COMMISSION E

.2 I WASHINGTON. D. C. 20555

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NOV I 5 1984 Mr. David A. Leach, President Pcwer Component Systems, Inc.

528 College Parkway, Suite H Annapolis, Maryland 21401

Dear Mr. Leach:

Thank you for stopping by on November 8, 1984, and providing me information on the blanket insulation manufactured by Insulation Technology, Inc.

As I indicated to you, I plan to foward copies of this information to NRC's

' Public Document Rocm and will reference Alden Research Laboratory's report in the staff's technical findings related to USI A-43, Containment Emergency Sump Performance.

Due to the plantispecific nature of sump or suction strainer blockage potential, anyJassessments of the safety implications of this insulation (or any other types of insulation) will be carried out as sart of the staft's plant-specific safety evaluations, and not on a generic sasis.

Thank you again for providing this information and for permission to place it into the public demain.

Sincerely, h

ab A. W. Se'kiz Task Manager r

Generic Issues Branch Division cf Safety Technology cc:

F. Schroeder K. Kniel tlRCPpR I

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