ML20236P662

Amend 133 to License NPF-1,revising Steam Generator Tube Plugging Criteria Based on Use of F* Distance Criteria

ML20236P662
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	08/07/1987
From:	Knighton G Office of Nuclear Reactor Regulation
To:
Shared Package
ML20236P660	List: ML20236P658 ML20236P662 ML20236P673
References
NUDOCS 8708120460
Download: ML20236P662 (9)

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ps or I o UNITED STATES

((" , v. NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20$55 5  :

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\...../

PORTLAND GENERAL ELECTRIC COMPANY l

THE CITY OF EUGENE, OREGON

]

PACIFIC POWER AND LIGHT COMPANY DOCKET NO. 50-344 i TROJAN NUCLEAR PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.133 License No. NPF-1

1. The Nuclear Regulatory Comission (the Commission) has found that:

A. The application for amendment by Portland General Electric Company, et al., (the licensee) dated February 20, 1987, as revised XprTT 20, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's l regulations set forth in 10 CFR Chapter I; l B. The facility will operate in confonnity with the application, the provisions of the Act, and the regulations of the Comission-C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health I

and safety of the public, and (ii) that such activities will be l conducted in compliance with the Comission's regulations; D. The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and l

E. The issuance of this amendment is in accordance with 10 CFR Part t

51 of the Comission's regulations and all applicable requirements i have been satisfied.

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8708120460 PDR 870807ADOCK 05000344 PDR P

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2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-1 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.133, are hereby.

incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifica-tions, except where otherwise stated in specific license conditions.

3. This license amendment is effective as of the date of its issuance. I FOR THE NUCLEAR REGU ATORY COMMISSION 1

Q[j " , ll{ &f George . Knig ton irector Projec Director V Division of Reactor Projects - III, IV, V and Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: August 7, 1987 I

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August 7, 1987-ATTACHMENT TO LICENSE AMENDMENT NO.133 TO FACILITY-0PERATING LICENSE N0. NPF-1 DOCKET NO. 50-344 Revise Appendix A as follows:

Remove Pages. ' Insert Pages TS 3/4 4-7 TS 3/4 4-7 3/4 4-8 3/4 4-8

'3/4 4-9 3/4 4-9 3/4 4-9a 3/4 4-9a 3/4 4-9b 3/4 4-9b B 3/4 4-2a B 3/4 4-2a i

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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) i

1. All nonplugged tubes that previously had detectable wall penetrations (>20%).

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. In addition to the 3% sample, all tubes with defects below the F* distance which have not been plugged shall be inspected in the tube sheet region.

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

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

2. The inspections include those portions of the tubes where 111perf ections were previously found.

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

Category Inspection Results C-1 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 (>10%) f urther wall penetrations to be included in the above percentage calculations.

TROJAN-UNIT 1 3/44-7 Amendment No. 67,133 August 7, 1987

l l- REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) l '

4.4.5.3 Inspection Frequencies - The above required. inservice inspections of steam generator tubes shall be performed at the following frequencies:

a. The first inservice inspection shall be performed after 6 i

Ef f ective Full Power Months but within 24 calendar months of l-initial criticality. Subsequent inservice inspections shall be perf ormed at intervals of not less than.12 nor more than 24 calendar months af ter the previous inspection. If two consecu-tive inspections following service under AVT conditions, not including the preservice inspection, result in all inspection results f alling into the C-1 categcry or if two consecutive inspections demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the~ inspection interval may be extended to a maximum of once per 40 months. l

b. If the results of the inservice inspection of a steam gen-erator conducted in accordance with Table 4.4-2 at 40 month intervals fall in Category C-3, the inspection frequency shall be increased to at least once per 20 months. The increase in inspection frequency shall apply until the subsequent inspections satisfy the criteria of Specifica-  !

tion 4.4.5.3.a; the interval may then be extended to a maximum of once per 40 months.

c. Additional, unscheduled inservice inspections shall be performed on each steam generator in accordance with the first sample inspection specified in Table 4.4-2 during the shutdown subsequent to any of the following conditions:

Primary-to-secondary tube leaks (not including leaks i 1.

originating f rom tube-to-tube sheet welds) in excess of the limits of Specification 3.4.6.2.

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2. A seismic occurrence greater'than the Operating Basis Earthquake.

3. A loss-of-coolant accident requiring actuation of the engineered safeguards.

4. A main steam line or feedwater line break.

I 3/4 4-8 Amendment No. 67,133 TROJAN-UNIT 1 August 7,1987 j l

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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.4 Acceptance Criteria

a. As used in the Specification:

1. Imperfection means an exception to the dimensions, finish or contour of a tube from that required by fabrication drawings or specifications. Eddy-current testing indica-tions below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections.

2. Degradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube.

3. Degraded Tube means a tube containing imperfections >20%

of the nominal wall thickness caused by degradation.

4.  % Degradation means the percentage of the tube wall thickness affected or removed by degradation.

5. Defect means an imperfection of such severity that it exceeds the plugging limit. A tube containing a defect is defective.

6. Plucoina Limit means the imperfection depth at or beyond which the tube shall be removed from service because it may become unserviceable prior to the next inspection and is equal to (40)% of the nominal tube wall thickness. This definition does not apply to the area of the tube sheet region below the F* distance, provided the tube has no indications of cracking within the F* distance.

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

8. Tube Inspection means an inspection of the steam generator tube f rom the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg.

TROJAN-UNIT 1 3/4 4-9 Amendment No. 67,133 August 7, 1987 l

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS'(Continued) 9, Preservice Inspection means an inspection of the full length of each tube in each steam generator performed by eddy current techniques prior to service to establish a baseline condition of the tubing. This inspection shall be performed af ter the field hydrostatic test ar.d prior to initial POWER OPERATION using the equipment and techniques' expected to be used during subsequent inservice inspections.

10. Tube Roll Expansion is that portion of a tube which has been increased in diameter by a rolling process such that no crevice exists between the outside diameter of the tube and the tube sheet.

11. F* Distance is the minimum length of the roll expanded portion of the tube which cannot contain any indications of cracking in order to ensure the tube does not pull out of the tube sheet. The F* distance is 1.4 inches and is measured f rom the top of the roll expansion of the tube down toward the '

bottom of the tube sheet.

b. The steam generator shall be determined OPERABLE after completing i the corresponding actions (plug all tubes exceeding the plugging limit) required by Table 4.4-2.

4.4.5.5 Reports

a. Following each inservice inspection of steam generator tubes, the number of tubes plugged 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 reported on an annual basis for the period in which the inspection was completed. This report shall ,

1 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.

c. Results of steam generator tube inspections which fall into Category C-3 shall be reviewed for deportability pursuant to '

Specification 6.6.1. If the results are deemed reportable, such report must be submitted to the Commission prior to the resumption of plant operation.

TROJAN-UNIT 1 3/4 4-9a Amendment No. 67,133 August 7,1987

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

d. The results of inspections of all tubes which have defects below the F* distance, but which were not plugged, shall be reported to the Commission following the inspection and prior to the restart of the unit. The report shall include:

1. Identification of the applicable tubes, and

2. Location and size of the degradation.

TROJAN-UNIT 1 3/4 4-9b Amendment No.133 August 7, 1987

REACTOR COOLANT SYSTEM BASES 3/4.4.5 STEAM GENERATORS CONTINllED system and the secondary coolant system (primary-to-secondary leakage =

500 gallons per day per steam generator). Cracks having ; primary-to-  ;

secondary leakage less than this limit during operation will have an i adequate margin of safety to withstard 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 pla.. shutdown and an unscheduled inspection, during which the leaking tubes will be located j and plugged.

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 l generator tube examinations. Plugging will be required of all tubes with imperfections exceeding the plugging limit which, by the definition of Specification 4.4.5.4.a is 40% of the tube nominal wall thickness.

Tubes with defects below the F* distance do not have to be plugged or repaired as long as there are no indications of cracking in the F* dis-tance. The F* distance is 1.4 inches and includes a safety factor of 3 and a 0.5-inch eddy current measurement uncertainty. Steam generator  !

tube inspections of operating plents have demonstrated the capability to i reliably detett wastage-type degradation that has penetrated 20% of the l l 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 cperation. 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.

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 f rom the Reactor Coolant Pressure Boundary. These detection systems hre consistent with the recommendations of Regulatory Guide 1.45, " Reactor Coolant Pressure Boundary Leakage Detection Systems", May 1973.

TROJAN-UNIT 1 B 3/4 4-2a Amendment No. ET ,133 August 7, 1987 l

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