ML17328A308

Proposed Tech Specs Authorizing Use of Steam Generator Sleeves to Repair Defective Steam Generator Tubes

ML17328A308
Person / Time
Site:	Cook
Issue date:	06/27/1990
From:	INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17328A307	List: ML17328A305 ML17328A308 ML17328A309
References
NUDOCS 9007060161
Download: ML17328A308 (45)

Text

ATTACHMENT 2 TO AEP:NRC:1129 PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS 900706016i 900627 PDR ADOCK 05000315 1

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REACTOR COOLANT SYSTEM SURVEILLANCE RE UIREMENTS Continued

1. All tubes that previously had detectable wall penetrations (greater than or equal to 20%) that have not been plugged or repaired by sleeving in the affected area.

2. Tubes in those areas where experience has indicated potential problems.

3. A tube inspection (pursuant to Specification 4.4.5.4.a.8) shall be performed on each selected tube. If any selected tube does not permit the passage of the eddy current probe for a tube inspection, this shall be recorded and an adjacent tube shall be selected and subjected to a tube inspection.

c. The tubes selected as the second and third samples (if required by Table 4.4-2) during each inservice inspection may be subjected to a partial tube inspection provided:

1. The tubes selected for the samples include the tubes from those areas of the tube sheet array where tubes with imperfections were previously found.

2. The inspections include those portions of the tubes where imperfections were previously found.

The results of each sample inspection shall be classified into one of the following three categories:

~Cate or Ins ection Results C-l Less than 5% of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.

C-2 One or more tubes, but not more than 1% of the total tubes inspected are defective, or between 5% and 10% of the total tubes inspected are degraded tubes.

C-3 More than 10% of the total tubes inspected are degraded tubes or more than 1% of the inspected tubes are defective.

Note: In all inspections, previously degraded tubes must exhibit significant (greater than or equal to 10%) further wall penetrations to be included in the above percentage calculations.

COOK NUCLEAR PLANT - UNIT 1 3/4 4-8 AMENDMENT NO.

REACTOR COOLANT SYSTEM SURVEILLANCE RE UIREMENTS Continued 4.4.5.4 Acce tance Criteria As used in this Specification:

contour of a tube or sleeve from that required by fabrication drawings or specifications. Eddy-current testing indications below 20% of the nominal wall thickness, considered as imperfections.

if detectable, may be general corrosion occurring on either inside or outside of a tube or sleeve.

De raded Tube or Sleeve means an imperfection greater than or equal to 20% of the nominal wall thickness caused by degradation.

Percent De radation means the amount of the wall thickness affected or removed by degradation.

Defect means an imperfection of such severity that the repair limit.

it exceeds Re air Plu in Limit means the imperfection depth at or beyond which the tube or sleeved tube shall be repaired or removed from service. Any tube which, upon inspection, exhibits tube wall degradation of 40 percent or more of the nominal tube wall thickness shall be plugged or repaired prior to returning the steam generator to service. Any sleeve which, upon inspection, exhibits wall degradation of 29 percent or more of the nominal wall thickness shall be plugged prior to returning the steam generator to service. In addition, any sleeve exhibiting any measurable wall loss in sleeve expansion transition or weld zones shall be plugged.

Unserviceable describes the condition of a tube or sleeve it leaks or contains a defect large enough to affect its if structural integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break as specified in 4.4.5.3.c, above.

Ins ection determines the condition of the steam generator tube or sleeve from the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg.

~dleevin a tube is permitted only in areas where the sleeve spans the tubesheet area and whose lower joint is at the primary fluid tubesheet face.

COOK NUCLEAR PLANT - UNIT 1 3/4 4-10 AMENDMENT NO.

REACTOR COOLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued The steam generator shall be determined OPERABLE after completing the corresponding actions (plugging or sleeving all tubes exceeding the repair limit and all tubes containing through-wall cracks) required by Table 4.4-2.

Steam generator tube repairs may be made in accordance with the methods described in either WCAP-12623 or CEN-313-P.

4.4.5.5 ~Re orts Following each inservice inspection of steam generator tubes, there are any tubes requiring plugging or sleeving, the number of if tubes plugged or sleeved in each steam generator shall be reported to the Commission within 15 days.

b. The complete results of the steam generator tube inservice inspection shall be included in the Annual Operating Report for the period in which this inspection was completed. This report shall include:

1. Number and extent of tubes inspected.

2. Location and percent of wall-thickness penetration for each indication of an imperfection.

3. Identification of tubes plugged or sleeved.

Results of steam generator tube inspections which fall into Category C-3 and require prompt notification of the Commission shall be reported pursuant to Specification 6.9.1 prior to resumption of plant operation. The written followup of this report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.

COOK NUCLEAR PLANT - UNIT 1 3/4 4-11 AMENDMENT NO.

e TABLE 4.4-2 STEAM GENERATOR TUBE INSPECTION 1ST SAMPLE INSPECTION 2ND ample Size Result Action Re uired Result Action Re uired Result A minimum C-1 None N/A N/A N/A N/A of S Tubes per S.G.

C-2 Plug or sleeve C-1 None N/A N/A defective tubes and inspect C-2 Plug or sleeve C-1 None additional 2S defective tubes C-2 Plug or sleeve tubes in this and inspect defective tubes S.G. additional 4S C-3 Perform action tubes in this for C-3 result S.G. of first sample C-3 Perform action N/A N/A for C-3 result of first sample C-3 Inspect all All other None N/A N/A tubes in this S.G.s are S.G., plug or C-1 sleeve defective tubes, and inspect 2S tubes in each tionn other S.G.

Some S.G.s Perform action N/A N/A C-2 but no for C-2 result additional of second sample Prompt noti- S.G. are fication to C-3 NRC pursuant to specifica-

6. 9. 1 Additional Inspect all tubes S.G. is in each S.G. and C-3 plug or sleeve N/A defective tubes.

Prompt notifica-tion to NRC pursuant to specification 6.9.1 S - 3 (N/n)% Where N is the number of steam generators in the unit, and n is the number of steam generators inspected during an inspection COOK NUCLEAR PLANT - UNIT 1 3/4 4-13 AMENDMENT NO.

REACTOR COOLANT SYSTEM BASES 3 4.4.5 STEAM GENERATORS TUBE INTEGRITY The Surveillance Requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS will be maintained. The program for inservice inspection of steam generator tubes is based on a modification of Regulatory Guide 1.83, Revision l.

Inservice inspection of steam generator tubing is essential in order to maintain surveillance of the conditions of the tubes in the event that there is evidence of mechanical damage or progressive degradation due to design, manufacturing errors, or inservice conditions that lead to corrosion.

Inservice inspection of steam generator tubing also provides a means of characterizing the nature and cause of any tube degradation so that corrective measures can be taken.

The plant is expected to be operated in a manner such that the second-ary coolant will be maintained within those chemistry limits found to result in negligible corrosion of the steam generator tubes. If the secondary coolant chemistry is not maintained within these parameter limits, localized corrosion may likely result in stress corrosion cracking. The extent of.

cracking during plant operation would be limited by the limitation of steam generator tube leakage between the primary coolant system and the secondary coolant system (primary-to-secondary leakage 500 gallons per day per steam generator). Cracks having a primary-to-secondary leakage less than this limit during operation will have an adequate margin of safety to withstand the loads imposed during normal operation and by postulated accidents. Operating plants have demonstrated that primary-to-secondary leakage of 500 gallons per day per steam generator can readily be detected by radiation monitors of steam generator blowdown. Leakage in excess of this limit will require plant shutdown and an unscheduled inspection, during which the leaking tubes will be located and plugged or sleeved. A steam generator while undergoing crevice flushing in Mode 4 is available for decay heat removal and is operable/operating upon reinstatement of auxiliary or main feed flow control and steam control.

Wastage-type defects are unlikely with the all volatile treatment (AVT) of secondary coolant. However, even if a defect of similar type should develop in service, it will be found during scheduled inservice steam generator tube examinations. Plugging or sleeving will be required for all tubes with imper-fections exceeding the repair limit which is defined in Specification 4.4.5.4.a. Steam generator tube inspections of operating plants have demonstrated the capability to reliably detect degradation that has penetrated 20% of the original tube wall thickness.

Whenever the results of any steam generator tubing inservice inspection fall into Category C-3, these results will be promptly reported to the Commission pursuant to Specification 6.9.1 prior to resumption of plant operation. Such cases will be considered by the Commission on a case-by-case basis and may result in a requirement for analysis, laboratory examinations, tests, additional eddy-current inspection, and revision of the Technical Specifications, if necessary.

COOK NUCLEAR PLANT - UNIT 1 B 3/4 4-2a AMENDMENT NO.

REACTOR COOLANT SYSTEM BASES Degraded steam generator tubes may be repaired by the installation of sleeves which span the section of degraded steam generator tubing. A steam generator tube with a sleeve installed meets the structural requirements 'of tubes which are not degraded.

To determine the basis for the sleeve plugging limit, the minimum sleeve wall thickness was calculated in accordance with Draft Regulatory Guide 1.121 (August 1976). In addition, a combined allowance of 20 percent of wall thickness is assumed for eddy current testing inaccuracies and continued operational degradation per Draft Regulatory Guide 1.121 (August 1976).

The following sleeve designs have been found acceptable by the NRC staff:

1. Westinghouse Mechanical Sleeves (WCAP-12623)

2. Combustion Engineering Leak Tight Sleeves (CEN-313-P)

Descriptions of other future sleeve designs shall be submitted to the NRC for review and approval in accordance with 10CFR50.90 prior to their use in the repair of degraded steam generator tubes. The submittals related to other sleeve designs shall be made at least 90 days prior to use.

3 4.4.6 REACTOR COOLANT SYSTEM LEAKAGE 3 4.4.6.1 LEAKAGE DETECTION SYSTEMS The RCS leakage detection systems required by this specification are provided to monitor and detect leakage from the Reactor Coolant Pressure Boundary. These detection systems are consistent with the recommendations of Regulatory Guide 1.45, "Reactor Coolant Pressure Boundary Leakage Detection Systems," May 1973.

3 4.4.6.2 OPERATIONAL LEAKAGE Industry experience has shown that while a limited amount of leakage is expected from the RCS, the unidentified portion of this leakage can be reduced to a threshold value of less than 1 gpm. This threshold value is sufficiently low to ensure early detection of additional leakage.

The 10 GPM IDENTIFIED LEAKAGE limitations provides allowance for a limited amount of leakage from known sources whose presence will not interfere with the detection of UNIDENTIFIED LEAKAGE by the leakage detection systems.

The CONTROLLED LEAKAGE limitation restricts operation when the total flow supplied to the reactor coolant pump seals exceeds 52 GPM. This limitation is based on the maximum seal injection flow capability of the Reactor Coolant Pumps and ensures a maximum safety injection flow assumed in the accident analysis.

COOK NUCLEAR PLANT - UNIT 1 B 3/4 4-3 AMENDMENT NO.

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CAW-90-045 AFFIDAVIT COMMONWEALTH OF PENNSYLVANIA:

ss COUNTY OF ALLEGHENY:

Before me, the undersigned authority, personally appeared Robert A. Wiesemann, who, being by me duly sworn according to law, deposes and says that he is authorized to execute this Affidavit on behalf of Westinghouse Electric Corporation ("Westinghouse" ) and that the averments of fact set forth in this Affidavit are true and correct to the best of his knowledge, information, and belief:

Robert A. Wiesemann, Manager Regulatory and Legislative Affairs of, Sworn before to me and subscribed this El S7 day 1990.

, Notary Public

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CAW-90-045 (1) I am Manager, Regulatory and Legislative Affairs, in the Nuclear and Advanced Technology Division, of the Westinghouse Electric Corporation and as such, I have been specifically delegated the function of reviewing the proprietary information sought to be withheld from public disclosure in connection with nuclear power plant licensing and rulemaking proceedings, and am authorized to apply for its withholding on behalf of the Westinghouse Energy Systems Business Unit.

(2) I am making this Affidavit in conformance with the provisions of 10CFR Section 2.790 of the Commission's regulations and in conjunction with the Westinghouse application for withholding accompanying this Affidavit.

(3) I have personal knowledge of the criteria and procedures utilized by the Westinghouse Energy Systems Business Unit in designating information as a trade secret, privileged or as confidential commercial or financial information.

(4) Pursuant to the provisions of paragraph (b)(4) of Section 2.790 of the Commission's regulations, the following is furnished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure should be withheld.

(i) The information sought to be withheld from public disclosure is owned and has been held in confidence by. Westinghouse.

CAW-90-045 (ii) The information is of a type customarily held in confidence by Westinghouse and not customarily disclosed to the public.

Westinghouse has a rational basis for determining the types of information customarily held in confidence by it and, in that connection, utilizes a system to determine when and whether to hold certain types of information in confidence. The application of that system and the substance of that system constitutes Westinghouse policy and provides the rational basis required.

Under that system, information is held in confidence if it falls in one or more of several types, the release of which might result in the'oss of an existing or potential competitive advantage, as follows:

(a) The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.) where prevention of its use by any of Westinghouse's competitors without license from Westinghouse constitutes a competitive economic advantage over other companies.

(b) It consists of supporting data, including test data, relative to a process (or component, structure, tool, method, etc.), the application of which data secures a competitive economic advantage, e.g., by optimization or improved marketability.

e CAW-90-045 (c) Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product.

(d) It reveals cost or price information, production capacities, budget levels, or commercial strategies of Westinghouse, its customers or suppliers.

(e) It reveals aspects of past, present, or future Westinghouse or customer funded development plans and programs of potential commercial value to Westinghouse.

(f) It contains patentable ideas, for which patent protection may be desirable.

(g) It is not the property of Westinghouse, but must be treated as proprietary by Westinghouse according to agreements with the owner.

There are sound policy reasons behind the Westinghouse system which include the following:

(a) The use of such information by Westinghouse gives Westinghouse a competitive advantage over its competitors.

It is, therefore, withheld from disclosure to protect the Westinghouse competitive position.

CAW-90-045 (b) It is information which is marketable in many ways. The extent to which such information is available to competitors diminishes the Westinghouse ability to sell products and services involving the use of the information.

(c) Use by our competitor would put Westinghouse at a competitive disadvantage by reducing his expenditure of resources at our expense.

(d) Each component of proprietary information pertinent to a particular competitive advantage is potentially as valuable as the total competitive advantage. If competitors acquire components of proprietary information, any one component may be the key to the entire puzzle, thereby depriving Westinghouse of a competitive advantage.

(e) Unrestricted disclosure would jeopardize the position of prominence of Westinghouse in the world market, and thereby give a market advantage to the competition of those countries.

(f) The Westinghouse capacity to invest corporate assets in research and development depends upon the success in obtaining and maintaining a competitive advantage.

CAW-90-045 The information is being transmitted to the Commission in confidence and, under the provisions of 10CFR Section 2.790, it is to be received in confidence by the Commission.

The information sought to be protected is not available in public sources or available information has not been previously employed in the same original manner or method to the best of our knowledge and belief.

The proprietary information sought to be withheld in this submittal is that which is appropriately marked in "American Electric Power D.C. Cook Unit 1 Steam Generator Sleeving Report (Mechanical Sleeves)" for D. C. Cook Unit 1, WCAP-12623, (Proprietary) being transmitted by American Electric Power (AEP) letter and Application for Withholding Proprietary Information from Public Disclosure, S. J. Brewer, Manager, Nuclear Safety 5 Licensing, AEP, to Document Control Desk, attention Dr. Thomas Hurley, June, 1990. The proprietary information as submitted for use by American Electric Power for D. C. Cook Unit 1 is expected to be applicable in other licensee submittals in response to certain NRC requirements for justification of a license amendment to permit the repair of generator tubes using sleeves.

This information is part or that which will enable Westinghouse to:

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CAW-90-045 (a) Provide documentation of the analyses, methods, acceptance criteria, and testing used for developing process parameters utilized to install sleeves in steam generator tubes to repair degraded or defective tubes.

(b) Provide a description of the tube sleeve installation tooling and qualification process.

(c) Establish the minimum wall thickness of sleeves in compliance with Regulatory Guide 1. 121.

(d) Demonstrate structural integrity of the repaired tube.

(e) Demonstrate no adverse impact on safety analyses and operation due to sleeve flow effects.

(f) Demonstrate capability to inspect the repair configuration using eddy current techniques as recommended in Regulatory Guide 1.83.

(g) Discuss features of installation tooling and process which will keep occupational radiation exposure as low as reasonably achieveable (ALARA).

(h) Assist the'customer to obtain NRC approval.

Further this information has substantial commercial value as follows:

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CAW-90-045 (a) Westinghouse plans to sell the use of similar information to its customers for purposes of meeting NRC requirements for licensing documentation.

(b) Westinghouse can sell support and defense of the technology to its customers in the licensing process.

Public disclosure of this proprietary information is likely to cause substantial harm to the competitive position of Westinghouse because it would enhance the ability of competitors to provide similar analytical documentation and licensing defense services for commercial power reactors without commensurate expenses. Also, public disclosure of the information would enable others to use the information to meet NRC requirements for licensing documentation without purchasing the right to use the information.

The development of the technology described in part by the information is the result of applying the results of many years of experience in an intensive Westinghouse effort and the expenditure of a considerable sum of money.

In order for competitors of Westinghouse to duplicate this information, similar technical programs would have to be performed and a significant manpower effort, having the requisite" talent and experience,'ould have to be expended for system design and performing tests.

Further the deponent sayeth not.

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ATTACHMENT 6 TO AEP:NRC:1129 COMBUSTION ENGINEERING, INCORPORATED AFFIDAVIT PURSUANT TO 10CFR 2.790

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AFFIDAVIT PURSUANT TO 10 CFR 2.790 Combustion Engineering, Inc.

State of Connecticut County of Hartford SS.:

I, E. H. Kennedy, depose and say that. I am the Manager, Nuclear Systems Licensing, of Combustion Engineering, Inc., duly authorized to make this affidavit, and have reviewed or caused to have reviewed the information which is identified as proprietary and referenced in the paragraph immediately below. I am submitting this affidavit in conformance with the provisions of 10 CFR 2.790 of the Commission's regulations for withholding this information.

The information for which proprietary treatment is sought is contained in the following document:

CEN-313-P, Revision 4-P, D. C. Cook Unit 1 Steam Generator Tube Repair Using Leak Tight Sleeves, Final Report, June 1990.

This document has been appropriately designated as proprietary.

I have personal knowledge of the criteria and procedures utilized by Combustion Engineering in designating information as a trade secret, privileged or as confidential commercial or financial information.

Pursuant to the. provisions of paragraph (b) (4) of. Section 2.790 of the Commission s regulations, the following is furnished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure, included in the above referenced document, should be withheld.

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1. The information sought to be withheld from public disclosure is the design, analysis and testing of leak tight sleeves used to repair degraded steam generator tubes in pressurized water reactors, which is owned and has been held in confidence by Combustion Engineering.

2. The information consists of test data or other similar data concerning a process, method or component, the application of which results in substantial competitive advantage to Combustion Engineering.

3. The information is of a type customarily held in confidence by Combustion Engineering and not customarily disclosed to the public. Combustion Engineering has a rational basis for determining the types of information customarily held in confidence by it and, in that connection, utilizes a system to determine when and whether to hold certain types of information in confidence. The details of the aforementioned system were provided to the Nuclear Regulatory Commission via letter DP-537 from F. M. Stern to Frank Schroeder dated December 2, 1974.

This system was applied in determining that the subject document herein is proprietary.

4. The information is being transmitted to the Commission in confidence under the provisions of,10 CFR 2.790 with the understanding that it is to be received in confidence by the Commission.

5.~ The information, to the best of my knowledge and belief, is not available in public sources, and any disclosure to third

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parties has been made pursuant to regulatory provisions or

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3 proprietary agreements which provide for maintenance of the information in confidence.

6. Public disclosure of the information is likely to cause substantial harm to the competitive position of Combustion Engineering because:

a. A similar product is manufactured and sold by major pressurized water reactor competitors of Combustion Engineering.

b. Development of this information by C-E required tens of thousands of manhours and millions of dollars. To the best of my knowledge and belief a competitor would have to undergo similar expense in generating equivalent information.

c. In order to acquire such information, a competitor would also require considerable time and inconvenience to design, analyze and test leak tight sleeves to repair degraded steam generator tubes in pressurized water reactors.

d. The information required significant effort and expense to obtain the licensing approvals necessary for application of the information. Avoidance of this expense would decrease a competitor's cost in applying the information and marketing the product to which the information is applicable.

e. The information consists of the design, analysis and testing of leak tight sleeves used to repair degraded steam generator tubes in pressurized water reactors, the application of which provides a competitive economic advantage. The availability of such information to competitors would enable them to modify their product to better compete with Combustion Engineering, take marketing or other actions to improve their product's position or

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impair the position of Combustion Engineering's product, and avoid

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developing similar data and analyses in support of their processes, methods or apparatus.

In pricing Combustion Engineering's products and services, significant research, development, engineering, analytical, manufacturing, licensing, quality assurance and other costs and expenses must be included. The ability of Combustion Engineering's competitors to utilize such information without similar expenditure of resources may enable them to sell at prices reflecting significantly lower costs.

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~ Use of the information by competitors in the international marketplace would increase their ability to market

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nuclear steam supply systems by reducing the costs associated with their technology development. In addition, disclosure would have an adverse economic impact on Combustion Engineering's potential for obtaining or maintaining foreign licensees.

Further the deponent sayeth not.

E. H. Keogh y Manager Nuclear Systems Licensing S worn to before m

'his~I')~~ day of 1990

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ATTACHMENT 7 TO AEP:NRC:1129 CERTIFICATE OF RECEIPT FOR SECURITY DOCUMENT TRANSMITTAL

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ertificate of Receipt For Security Document Transmittal 6.2, Attach. 2 Safeguards Information Withhold From Public Disclosure Safeguards and 10 CFR 2.790 information Transmittal and Acknowledgement To. USNRC NRR Date tjrCAP-12623, D.C. Cook Unit 1 Steam Generator Sleeving Report Document Description Rebecca Green 1 Riverside plaza,Columbus Ohio 43215 Return Signed Transmittal Within Two Weeks To:

(Name/Location)

Revisions and/or Additions No. Other f re uest for amendment to T/S GENERAL INSTRUCTIONS:

1. When in use, Safeguards and 10 CFR 2.790 Information shall be under the immediate control of an individual who has a need to know. When unattended, Safeguards Information must be stored in an approved, locked security storage container and 10 CFR 2.790 Information must be stored in a Locked environment (such as a desk, file cabinet, storage room).

2. When transmitting Safeguards or 10 CFR 2.790 Information, a double envelope system shall be utilized. The inner envelope shall be clearly marked, "Safeguards Information, Withhold From Public Disclosure, Unauthorized Disclosure is Subject to Civil and Criminal Sanctions, Open by Addressee Only," or "10 CFR 2.790 Information, to be Opened by Addressee Only." The outer envelope shall be addressed using standard mailing procedures. All transmittals of Safeguards and 10 CFR 2.790 Information require the use of an acknowledgement form.

3. Safeguards and 10 CFR 2.790 Information may be duplicated to the minimum extent necessary without permission from the originator.

SPECIAL INSTRUCTIONS:

Acknowledgement I have received the document(s) forwarded to me and have taken the following action:

O Reviewed, retained and assumed control of document D Reviewed and returned document Upon Separation From Safeguards Pages, This Document ls Decontrolled Other Comments:

Signed: Date:

(Name/Location)

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WCAP-12623, D.C. Cook Unit 1 Steam Generator Sleevinci Report Document Description Rebecca Green 1 Riverside plaza, Columbus Ohio 43215 Return Signed Transmittal Within Two Weeks To (Name/Location) h Review and Comment Information Only

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"t= " ., GENERAL INSTRUCTIONS:

1. WI)en in use, Safeguards and 10 CFR 2.790 Information shall be under the immediate control of an individual who has a need to know. When unattended, Safeguards Information must be stored in an approved, locked security storage container and 10 CFR 2.790 Information must be stored in a Locked environment (such as a desk, file cabinet, storage room).

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acknowledgement form.

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3. Safeguards and 10 CFR 2.790 Information may be duplicated to the minimum extent necessary without permission from the originator.

SPECIAL INSTRUCTIONS:

Acknowledgement I have received the document(s) forwarded to me and have taken the following action:

~ IQ Reviewed, retained and assumed control of document Upon Separation From Safeguards Reviewed and returned document Pages, This Document ls Decontrolled

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f 90)'4S3 AMERICAN ELECTRIC American Electric Power System POWER Riverside Plaza, Columbus, Ohio 43215 (614) 223-1000 ertificate of Receipt For Security Document Transmittal Safeguards information Sl No -062590-02 G.P. 6.2, Attach. 2 Withhold From Public Disclosure Safeguards and 10 CFR 2.790 information Transmittal and Acknowledgement To Date (Name/Location)

CEN-313-P, D.C.'Cook'Unit 1 Steam Generator Tube Repair Using Leak Tight Sleeves Document Description Return Signed Transmittal Within Two Weeks To. 1 Riverside Plaza Columbus, OH NSGL'Name/Location) 43215 Attn. Rebecca Green O Information Only Revisions and/or Additions No. Other for re uest for amendment to T/S GENERAL INSTRUCTIONS:

1. When in use, Safeguards and 10 CFR 2.790 Information shall be under the immediate control of an individual who has a need to know. When unattended, Safeguards Information must be stored in an approved, locked security storage container and 10 CFR 2.790 Information must be stored in a Locked environment (such as a desk, file cabinet, storage room).

2. When transmitting Safeguards or 10 CFR 2.790 Information, a double envelope system shall be utilized. The inner envelope shall be clearly marked, "Safeguards Information, Withhold From Public Disclo'sure, Unauthorized Disclosure is Subject to Civil and Criminal Sanctions, Open by Addressee Only," or "10 CFR 2.790 information, to be Opened by Addressee Only." The outer envelope shall be addressed using standard mailing procedures. All transmittals of Safeguards and 10 CFR 2.790 Information require the use of an acknowledgement form.

3. Safeguards and 10 CFR 2.790 Information may be duplicated to the minimum extent necessary without permission from the originator.

I SPECIAL INSTRUCTIONS:

Acknowledgement I have received the document(s) forwarded to me and have taken the following action:

O Reviewed, retained and assumed control of document O Reviewed and returned document Upon Separation From Safeguards Pages, This Document is Decontrolled Other Comments:

Signed: Date:

(Name/Location)

Originator Copy - White Return to Sender - Canary Recipient Copy- Pink

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~American Electric Power System POI/IIER Riverside Plaza, Columbus, Ohio 43216 (614) 223-1000 p,,., ertificate of Receipt For Security Document Transmittal Safeguards Information SINo -062590-02 G P 62 Attach 2 Jh'afeguards Withhold From Public Disclosure and 10 CFR 2.790 Information Transmittal and Acknowledgement To: Date (Name/Location)

'I Unit 1 Steam Generator Tube Repair Using Leak Tight Sleeves Document Description-Retum Signed Traftsmittal Within Two Weeks To c- Power 1 Riverside Plaza Columbus,'H (Name/Location) 43215 Attn. Rebecca Green, NSaL I 1 Review and Comment Information Only r t Revisions and/or Additions No. Other S ort for re est for amendment to T/S

! I GENERAL INSTRUCTIONS

1. When in use, Safeguards and 10 CFR 2.790 Information shall be under the immediate control of an individual who has a need to know. When unattended, Safeguards Information must be stored in an approved, locked security storage container and 10 CFR 2.790 Information must be stored in a Locked environment (such as a desk, file cabinet, storage room).

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2. When transmitting Safeguards or10 CFR 2.790 Information, a double envelope system shall be utilized. The inner envelope shall be clearly marked, "Safeguards Information, Withhold From Public Disclosure, Unauthorized Disclosure is Subject to Civil and Criminal Sanctions, Open by Addressee Only," or "10 CFR 2.790 Information, to be Opened by Addressee Only." The'outer,envelop'e shall be I addressed using standard mailing procedures. All transmittals of Safeguards and 10 CFR 2.790 Information require the use of an

., acknowledgement form.

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3. Safeguards and 10 CFR 2.790 Information may be duplicated to the minimum extent necessary without permission from the originator.

SPECIAL INSTRUCTIONS:

Acknowledgement I have received the document(s) forwarded to me and have taken the following action:

A Reviewed, retained and assumed control of document I

Upon Separation From Safeguards Reviewed and returried document Pages, This Document Is Decontrolled Comments:

Signed: Date:

(Name/Location)

Originator Copy - White "g Return to Sender - Canary Recipient Copy - Pink

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