ML19261B290
| ML19261B290 | |
| Person / Time | |
|---|---|
| Issue date: | 01/31/1979 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Waite W TRANSCO, INC. |
| References | |
| NUDOCS 7902150260 | |
| Download: ML19261B290 (3) | |
Text
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JAN 31 1979 Mr. William Waite Senior Vice resident TRANSCO, Inc.
55 East Jackson Boulevard Chicago, Illinois 60604
SUBJECT:
TRANSCO, INC. LETTER REGARDING OWENS-CORNING FIBERGLAS TOPICAL REPORT OCF-1, NUCLEAR CONTAINMENT INSULATION SYSTEM Cear Mr. Waite:
Your letter of December 27, 1978 provided information that you wished us to consider prior to completing our review of the subject topical report.
Actually, our r3 view had been completed and our Topical Report Evaluation had been issued prior to receipt of your letter. A copy of our Evaluation is enclosed.
Even though our review of the topical report had been completed, we have carefully considered the points raised in your letter and conclude that a revision to our evaluation of the subject topical report is not needed.
The bases for this conclusion are discussed below.
The NRC staff's review of the Owens-Corning topical report considered:
(1) release of airborne particles leading to a radiation health hazard in service; (2) stress corrosion cracking of the austenitic stain-less steel surfaces that come in contact with the insulation; (3) deterioration of the thermal properties during normal operation, complicating operation and control of the plant; (4) potential for creating fire hazard in the containment area that could interfere with safe operation of the plant; (5) interference with the emergency spray system in the event of a loss-of-coolant accident; and (6) blocking of pressure relief ports in the event of an accident.
We believe that these are the major safety considerations for this type of insulation. Our approvC of the topical report merely means that the NRC staff has determined th t the report is an acceptable reference for licensing actions.
It does not imply that the staff believes that it is superior to a competitive product or that it is suitable for every possible application. The licensee bears the primary responsibility for the selec-tion of all components and systems, including thermal insulation.
Many of the points mentioned in your letter were raised a number of years ago by members of the NRC staff and the Advisory Comittee on Reactor Safeguards.
This led to the issuance of a number of Regulatory Guides.
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Mr. William Waite JAM 3 1 eng As discussed below, one of these, Regulatory Guide 1.36, " Nonmetallic Thermal Insulation for Austenitic Stainless Steel," issued in February 1973, deals specifically with thermal insulation; and the others deal with general requirements for all components regarding shipping, storage, installation, inspection, housekeeping, and quality assurance during operation.
Position C.1 of Regulatory Guide 1.36 cautions:
"All insulating materials should be manufactured, processed, packaged, shipped, stored, and installed in a manner that will limit, to the maximum extent practical, chloride and fluoride contamination from external sources."
The specific criteria that the Nuclear Regulatory Commission uses for evaluation of thermal insulation to be used on austenitic stainless steel are the criteria of Regulatory Position C.2 (Qualification Test) of Regu-latory Guide 1.36.
The Position C.2 Qualification Test requires that a representative insulation sample pass an appropriate stress corrosion cracking test and comply with the Regulatory Guide Figure 1 chemical analyses limitation regarding leachable chloride, fluoride, sodium and silicate. The test data and information in the subject topical report show that the Nu'k'on insulation meets the guide and is qualified for use in light-water-cooled nuclear plants in this respect.
As your letter notes, there are a number of potential sources of radio-active or chemical contamination, especially during construction. These The sources apply to all plant components, not only thermal insulation.
NRC staff requires that all equipment and components that may affect plant safety be packaged, shipped, stored, installed, operated, and maintained There are in a manner to prevent radioactive and chemical contamination.
a number of Regulatory Guides that deal with this subject. Examples of these are Regulatory Guide 1.38, " Quality Assurance Requirerents for Packaging, Shipping, Receiving, Storage, and Handling of Items for Water-Cooled Nuclear Power Plants," Revision 2, issued in May 1977; Regulatory Guide 1.116, " Quality Assurance Requirements for Installation, Inspection, and Testing of Mechanical Equiprent and Systems," issued in May 1977; Regulatory Guide 1.39, " Housekeeping Requirements for Water-Cooled Nuclear Power Plants," Revision 2, issued in Septeater 1977; and Regulatory Guide 1.33, " Quality Assurance Program Requirements (Operations)," Revisior. 2, issued in March 1978. The NRC staff, as part of our plant specific review, requires that applicants develop a program to implement these Regulatory Guides or their equivalent.
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3I M Mr. William Waite NRC establishes general safety criteria, sets specific requirements, ar.d provides guidance in the form of Regulatory Guides or NUREG reports. The NRC staff performs inspections and audits to assure that programs are properly implemented. However, it should be noted that the licensees are the first line of defense to ensure safety of the public. They directly control plant design, construction, operation, and maintenance.
The licensees make the basic decision on suitability of specific products and are responsible to see that the plant is operated in accordance with NRC Regulations and in a manner to protect the health and safety of the public.
Based on the considerations discussed above, we believe that our review of Owens-Corning Fiberglas Topical Report 0CF-1, " Nuclear Containment Insula-tion System," was performed in an acceptable manner, and covered the major safety concerns. Therefore, we conclude that the topical report is accept-able for referencing on specific applications.
Sincerely, D. B. Vassallo, Assistant Director for Light Water Reactors Division of Project Management
Enclosure:
Topical Report Evaluation
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!'r. Cordon Pinsky Owens-Corning Fiberglas Corporation P. O. Dox 2196 Shawnee 11issiore, Kansas 06291
Dear Mr. Pinsky:
SUBJECT:
FINAL STAFF EVALUATIO!! CF TOPICAL P.EPORT OCF-1, NUCLEAR CONTAlii!!ENT INSULATIO;l SYSTEli The staff has corpleted its evaluation of the sub. ject tcoical recort on your ilu'k'on insulation system and finds it is accentable for ref-erence in licensing applications. A detailed evaluation of your report is enclosed.
Based on the results of the quantitative and qualitative tests per-formed by or for Quens-Corning Fiberglas, the staff concludes that the Daens-Corning Fiberglas Corporation's nuclear containment insu-lation systen (itu'k'on) is canable of retarding heat loss fron oining and equipment in containrent areas, and that the overall inteqrity of the blankets will not be adversely affected by the conditions
'fe also conclude that during found durino the lifetir.c of the plant.
a loss-of-coolant accident, the Owens-Corning Fiberclas insulation systen is not expected to interfere with the operation of the cr.crgency recirculation cooling systen.
A copy of this letter and its enclosure should be included in the front of the final revision to your report. This final revision should incorporate and update all additional submissions not yet incorporated into the basic report. Twenty-five copies of this final revision should be sent to the staff within sixty days.
Sincerely, Q-Robert L. Baer, Pronran "anager Light '.fater Reactors Creich ::n. C Division of Pro. ject ;ianage ent Office of Nuclear Reactor Regulaticn
Enclosure:
As stated
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Topical Report Evaluation Report Number and
Title:
OCF-1; Nuclear Containment Insulation System Originating Organization: Owens-Corning Fiberglas Corporation Sumary of Tooical Recort The topical report describes the design and testing of the Owens-Corning Fiberglas (CCF).'orporation's themal insulation system (Nu'K'on) for use in the containment areas of light water nuclear pcwer plants.
Nu'K'on is a blanket insulation consisting of Fiberglas insulating wool encapsulated in Fiberglas cloth.
It is reinforced with a Fiberglas scrim and sewn with Fiberglas thread. The insulation blanket will be held in place by the Velcro hook / loop fastening system. An optional stainless steel Jacket that acts as a protective cover over the blankets to prevent damage from abuse during installation and regular plant main-tenance, provides a means for holding the blanket in place during various -. --s postulated accidents. Non-Jacketed blankets are designed with secondary holding straps attached to the blanket and wrapped completely around it.
Nu'K'on is designed to withstand the containment area environment expected during nomal operations over the design life of the plant, and the predicted environment during the postulated loss of coolant acr.ident or a main steam line break accident.
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