ML17325A016
| ML17325A016 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 04/01/1987 |
| From: | Wigginton D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17325A017 | List: |
| References | |
| NUDOCS 8704060007 | |
| Download: ML17325A016 (17) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 II<DIANA AND t<ICIIIGA>) ELECTRIC COMPANY DOCKET NO. 50-315 DONALD C.
COOK NUCLEAR PLAt<T UNIT tl0.
1 AtiENDl'IENT TO FACILITY OPERATING I.ICENSE Amendment
>,'o. 103 License No.
DPR-58 1.
The Nuclear Regulatory Coriinission (the Commission) has found that:
A.
The application for amendment by Indiana and Hichigan Electric Company (the licensee) dated November 13, 1986, 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 authorized by this amendmert 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 COIIIIission's regulations and all applicable requirements have been satisfied.
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:
8704060007 870401 PDR ADQCK 05000315 P
(2)
Technical Specifications The. Technical Specifications contained in Appendices A and B, as revised through Amendment No.103, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The Technical Specifications are to become effective within 45 days of receipt of this amendment.
4.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMIMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance Dave L. Wigginton, Project Manager PWR Project Directorate ¹4 Division of PWR Licensing-A PWR¹4/DPWR-A DWiggjnton/rad
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0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA AND MICHIGAN ELECTRIC COMPANY DOC)iET NO. 50-316 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
89 License No.
DPR-74 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana and Michigan Electric Company (the licensee) dated November 13, 1986, coIIIplies 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 authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities wi11 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.
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-74 is hereby amended to read as follows:
'I
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.89
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Speci ficati ons.
3.
The Technical Specification changes are effective within 45 days of receipt of this amendment.
4.
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:
AP<<> ~
Dave L. Wigginton, Project Manager PWR Project Directorate ¹4 Division of PWR Licensing-A PWR¹4 DPWR-A DWigginton/rad
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ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 103FACILITY OPERATING LICENSE NO.
DPR-58 AMENDMENT NO, 89 FACILITY OPERATING LICENSE NO.
DPR-74 DOCKET NOS.
50-315 AND 50-316 Revise Appendix A as follows:
Remove Pa es Unit I 3/4 4-7 3/4 4-12 B3/4 4-2a Unit 2 3/4 4-7 3/4 4-8*
3/4 4-12 B3/4 4-2a Insert Pa es 3/4 4-7 3/4 4-12 B3/4 4-2a 3/4 4-7 3/4 4-8*
3/4 4-12 B3/4 4-2a
- Included for convenience only
REACTOR COOLANT SYSTEM STEAM GENERATOPS LIM'TING CONDITION FOR OPERATION 3.4.5 Each steam generator shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3 and 4".
ACTION:
With one or more steam generators inoperable, restore the inoperable generator(s) to OPERABLE status prior to increasing T
above 200'F.
avg SURVEILLANCE RE UIREMENTS 4.4.5.0 Each steam generator shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the require-ment of Specification 4.0.5.
4.4.5.1 Steam Generator Sam le Selection and Ins ection - Each steam generator shall be determined OPERABLE during shutdown by selecting and inspecting at least the minimum number of steam generators specified in Table 4.4-1.
4.4.5.2 Steam Generator Tube Sam le Selection and Ins ection - The steam generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table 4.4-2.
The inse. vice inspection of steam generator tubes shall be performed at the frequencies specified in Specification 4.4.5.3 and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 4.4.5.4.
The tubes selected for each inservice inspec-tion shall include at least 3%%d of the total number of tubes in all steam generators; the tubes selected for these inspections shall be selected on a random basis except:
1 a.
Where experience in similar plants with similar water chemistry indicates critical areas to be inspected, then at least 50/ of the tubes inspected shall be from these critical areas.
b.
The first sample of tubes selected for each inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:
This Specification does not apply in Mode 4 while performing crevice flushing as long as Limiting Conditions For Operation for Specification 3.4.1.3 are maintained.
D. C. Cook
. Unit 1 3/4 4-7 Amendment No. 103
TABLE 4.4-1 n00 I
r.
Preservice Inspection NINIHUN NUHBEf4 OF S7EW GENERÃIO
'LQ BE INSPEX."IKD IXJRING INSERVICE INSPECTION No. of Steam Generators per Unit First Inservice Inspection Second
& Subsequent Inservice Inspections Table Notation:
l.
We inservice inspection may be limited to one steam generator on a rotating schedule encclrpassing 3 N 4 of the tubes (where N is the number of steam generators in the plant) if the remits of the first or previous inspections indicate that all steam generators are perfonnirg in a like manner.
Note that under same circumstances, the operating conditions in one or more steam generators may be found to be more severe than those in other steam most severe conditions.
I tt R0 O
lA 2.
%he third and fourth stam generators not inspected during the first inservice inspection shall be inspected during the second and third inspections, respectively.
'Ihe fourth and'ubsequent inspections shall follcar the instructions described in 1 above.
S>F>
G"-N TOR TU II 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 generatortubing is essential in order to maintain surveillanc'e of the conditions of the tubes in the event tha" there is evidence of mechanical damage or progressive degradati.on 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 degrada=ion so that corrective measures can be taken.
The plant is expected to be operated in a manner such that the secondary 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 paramete.
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
'eakage 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 readi.ly 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.
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 wi.ll be required for all tubes wi.th imperfections exceeding the plugging limit which, by the definition of Specification 4.4.5.4.a is 40% of the tube nominal wall thickness, Steam generator tube inspections of operating, plants have demonstrated the capability to reliably detect degradation that has penetrated 20% of the ori.ginal 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.
D.
C.
COOK - UNIT 1 B 3/4 4-2a Amendment No. 103
REACTOR COOLANT SYSTEM STEAM GENERATOPS LIMITING CONDITION FOR OPERATION 3.4.5 Each steam generator shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3 and 4P ACTION:
With one or more steam generators inoperable, restore the inoperable generator(s) to OPERABLE status prior to increasing T
above 200'F.
avg SURVEILLANCE RE UIREHENTS 4.4.5.0 Each steam generator shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the require-ment of Specification 4.0.5.
4.4.5.1 Steam Generator Sam le Selection and Ins ection - Each steam generator shall be determined OPERABLE during shutdown by selecting and inspecting at least the minimum number of steam generators specified in Table 4.4-1.
4.4.5.2 Steam Generator Tube Sam le Selection and Ins ection - The steam generator tube minimum sample size, inspection result classification, and the corresponding action r equired shall be as specified in Table 4.4-2.
The inservice inspection of steam generator tubes shall be performed at the frequencies specified in Specification 4.4.5.3 and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 4.4.5.4.
The tubes selected for each inservice inspec-tion shall include at least 3'5 of the total number of tubes in all steam generators; the tubes selected for these inspections shall be selected on a random basis except:
a.
Where experierce in similar plants with similar water chemistry indicates critical areas to be inspected, then at least 50/ of the tubes inspected shall be from these critical areas.
b.
The first sample of tubes selected for each inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:
- This Specification does not apply in Node 4 while performing crevice flushing's long as LimitingConditions For Operation for Specification 3.4.1.3 are maintained.
D.C.
COOK - UNIT 2.
3/4 4-7 Amendment No.
89
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REACTOR COGLAiNT SYSTEM SURVEILLANCE RE JIREMENTS (Continued) 1.
All nonplugged tubes that previously had detectable wall penetra tions
(>20";).
2.
3.
Tubes in those areas where experience has indicated potential probl ems.
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 ari adjacent tube shall be selected and subjected to a tube inspectiop.
c.
The tubes selected as the second and third samples (if required by Table 4.4-2) durinq each inservice inspection may be subjected to a partial. tube inspection provided:
1.
The tubes selected for these 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 tiie tubes where imperfections were previously found.
The results of each sample inspection shall be classified into one o
the following three categories:
~Cate or.
C-1 Ins ection Results Less thari 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 (>105) further wall penetrations to be included in the above perceritage calculations.
D.C.
COOK - UNIT 2 3/4 4-8
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TABIZ 4.4-1 n00 f
r.
Ct Preservice Inspection MINIMUMNUMBER OF STEAN GERXMURS 'LQ BE INSPECT IX3RING INSERVICE INSPECTION No. of Steam Generators per Unit First Inservice Inspection Second
& Subsequent Inservice Inspections Table Notation:
0 l.
We inservice inspection may be limited to one steam generator on a rotating encatpasshxf 3 N 0 of the tubes (where N is the number of steam generators in the plant) if the results of the first or previous in.anions indicate that all steam generators are 31 M
W t9~
I one or more steam generators may be found to be more severe than those in other steam generators Under such circumstances the sample sequence shall be modified to inspect the most severe conditions.
%m third and fourth steam generators not inspected during the first inservice ~p shag.1 be inspected during the second and third inspections zespectivel j.
Wef~~
'ubsequent inspections shall foliar the instructions described in 1 above.
EACTOR COOLAN SYS E
AS S
3 4.4 TEAM GENERATOR BE INTEGRT 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 1.
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 secondary 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 limits, localized corrosion may likely result in stress corrosi.on 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 limi.t will require plant shutdown and an unscheduled inspection, during which the leaking tubes will be located and plugged.
A steam generator while undergoing crev'ice flushing in Node 4 is available for decay heat removal and is operable/operating upon reinstate-ment of auxiliary or main feed flow control and steam control.
.Wastage-type defects are unlikely with secondary coolant.
- However, even if a defect should develop in service, it will be found during scheduled inservice steam generator tube examinations.
Plugging will be required for all tubes with imperfections exceeding the plugging limit of 40% of the tube nominal wall thickness.
Steam generator tube inspections of operating plants have demonstrated the capability to reli.ably 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 wi.ll 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, D.
C.
COOK - UNIT 2 B 3/4 4-2a Amendment No.
89
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