ML17328A806
| ML17328A806 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/05/1990 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17328A807 | List: |
| References | |
| TAC-77109, NUDOCS 9012140100 | |
| Download: ML17328A806 (16) | |
Text
~8 REPy a)
O I
a 0
~y
+
~O
+a*++
UNITEDSTATES NUCLEAR REGULATORYCOMMISSION WASHINGTON,D. C. 20555 INDIANA MICHIGAN POMER.COMPANY DOCKET NO. 50-315 DONALD C.
COOK. NUCLEAR.PLANT UNIT NO..l AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 151 License No. DPR-58 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated June 27, 1990 and supplemented October 9, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility,will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authori2.'ed by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
90i2i40i00 901205 PDR ADOCK 050003i5 P
~ J, 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.
DPR-58 is hereby amended to read as follows:
Technical S ecifications
/
The Technical Specifications contained fn Appendices A and B, as revised through Amendment No. 151, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 5,
1990 Vcw
. B. Mar Director Project Directorate III-I Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE-AMENDMENT N0..151.
FACILITY OPERATING LICENSE NO. DPR-58 DOCKET N0.-50-315 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by.
amendment number and contain marginal lines indicating the area of change.
RENOVE 3/4 4-8 3/4 4-10 3/4 4-11 3/4 4-13 B3/4 4-2a B3/4 4-3 INSERT 3/4 4-8 3/4 4-10 3/4 4-11 3/4 4-13 B3/4 4-2a B3/4 4-3
L J
REACTOR COOLANT SYSTEM SURVEILLANCE RE UIREMENTS Continued l.
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.
I 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.'f 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:
~Caee orv Ins ection Results C-1 C-2 Less than 5$ of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.
One or more tubes, but not more than 1% of the total tubes inspected are defective, or b'etween 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 1'4 of the inspected tubes are defective.
Note:
In all inspections, previously degraded tubes must exhibit significant (greater than or equal to 10%) further wall I
penetrations to be included in the above percentage calculations.
COOK NUCLEAR PLANT - UNIT 1 3/4 4-8 AMENDMENT NO.
~
~
'f
REACTOR COOLANT SYSTEM SURVEILLANCE RE UIREMENTS Continued 4.4.5.4 Acce eence Criteria a.
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, if detectable, may be considered as imperfections.
2.
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.
4.
5.
Percent De radation means the amount of the wall thickness affected or removed by degradation.
C Defect means an imperfection of such severity that it exceeds the repair limit.
6.
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.
7.
Unserviceable describes the condition of a tube or sleeve if it leaks or contains a defect large enough to affect its 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.
8.
tube or sleeve from the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg.
9.
~Sleevin s tube is permitted only in trees 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.
PSp 151
~I l
REACTOR COOLANT SYSTEMS SURVEILLANCE RE UIREMENTS Continued The steam generator shall be determined OPERABLE after completing the corresponding ections (plugging or sleeving ell tubes exceeding the repair limit and all tubes containing through-wall cracks) required by Table 4.4-2.
c ~
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 R~e orts a ~
Following each inservice inspection of steam generator tubes, if there are any tubes requiring plugging.or sleeving, the number of 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.
9H p
~ ~1
f55
~ '
. I555
~
~
~
+
~
~ ~
~
~
Il
~
~
J I
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'o 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 dev'clop 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 whi'ch is defined in Specification 4.4.5.4.a.
Steam generator tube inspectionsof operating plants have demonstrated the capability to reliably detect degradation that has penetrated 20% of the original tube wall thickness.
B 3/4 4-2a 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 insp'ection, and revision of the Technical Specifications, if necessary.
COOK NUCLEAR PLANT - UNIT 1 AMENDMENT NO. f98, 151
l I
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 leakages 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. Q, QB" 51
~I g