ML17324A919
| ML17324A919 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 05/16/1986 |
| From: | Youngblood B Office of Nuclear Reactor Regulation |
| To: | Dolan J AMERICAN ELECTRIC POWER SERVICE CORP., INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| References | |
| NUDOCS 8605220502 | |
| Download: ML17324A919 (15) | |
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Docket Nos.:
50-315 and 50-316 Mr. John Dolan, Vice President Indiana and Michigan Electric Company c/o American Electric Power Service Corporation 1 Riverside Plaza
- Columbus, Ohio 43216
Dear Mr. Dolan:
ig WY 198~
Subject:
Technical Specification Requirements for Steam Generators Operable in Modes 1, 2, 3, and 4 - D.
C.
Cook Nuclear Plant, Units 1 and 2
In recent discussions with your staff, a discrepancy was brought to our attention concerning the Technical Specification requirements for steam generators operable in Modes 1, 2, 3, and 4.
For the D.
C.
Cook Nuclear Plant, Unit Nos.
1 and 2, the Technical Specification which has been de-termined to be inappropriately worded is Section 3.4.5 and the accompanying surveillance requirements.
It is the intent of this specification to ad-dress the required steam generators integrity and not the operability.
Technical Specification 3.4. 1 on the reactor coolant system defines oper-ability requirements in all modes and is unchanged by this determination.
In the enclosed copy of the Specification for Unit 1, we have marked up the changes which we would find acceptable as a clarification of the Technical Specifications.
It is requested that the Indiana and Michigan Electric Company propose to modify the Unit 1 and 2 Technical Specification with these changes at your next convenience.
This understanding has been discussed with Region III and they agree.
If there are any further questions on this subject, please let us know.
8605220502 860516 PDR ADOCN, 05000315 P
Enclosure:
As stated cc:
See next page Sincerely, B. J.
Youngblood, Director PWR Project Directorate ¹4 Division of PWR Licensing-A DISTRIBUTION:
NRC PDR Local PDR PRC System PWR¹4 Rdg BJYoungblood Rdg MDuncan PWR¹4/DPWR-A
- DWigginton/mac 05/05/86 DWigginton OELD ACRS (10)
JPartlow BGrimes EJordan PWR¹4/DPWR-A
- MDuncan 05/05/86 SEE PREVIOUS CONCURRENCES p gpss FOB/DPWR-A PWR¹4/DPWR-A
- VBenaroya QBJYoungblood 05/05/86 05/tg /86
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Mr. John Dolan Indiana and Michigan Electric Company Donald C.
Cook Nuclear Plant CC:
Mr. M. P. Alexich Vice President Nuclear Operations American Electric Power Service Corporation 1 Riverside Plaza
- Columbus, Ohio 43215 Attorney General Department of Attorney General 525 West Ottawa Street Lansing, Michigan 48913 Township Supervisor Lake Township Hall Post Office Box 818 Bridgman, Michigan 49106 W. G. Smith, Jr., Plant Manager Donald C.
Cook Nuclear Plant Post Office Box 458 Bridgman, Michigan 49106 U.S. Nuclear Regulatory Commission Resident Inspectors Office 7700 Red Arrow Highway Stevensvil 1 e, Michigan 49127 Gerald Charnoff, Esquire Shaw, Pittman, Potts and Trowbridge 1800 M Street, N.W.
Washington, DC 20036 Mayor, City of Bridgeman Post Office Box 366 Bridgman, Michigan 49106 Special Assistant to the Governor Room 1 - State Capitol Lansing, Michigan 48909 Nuclear Facilities and Environmental Monitoring Section Office Division of Radiological Health Department of Public Health 3500 N. Logan Street Post Office Box 30035 Lansing, Michigan 48909 The Honorable John E. Grotberg United States House of Representatives Washington, DC 20515 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen El lyn, Illinois 60137 J. Feinstein American Electric Power Service Corporation 1 Riverside Plaza
- Columbus, Ohio 43216
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REACTOR COOLANT SYSTEM STEAM GENERATO TosF lv're~
LIMITING CONDITION FOR OPERATION JLa.~~~~
3.4.5<gach steam generator shall be~ERA~.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
ill h << ~
h generator(s) prior to increasing T above 200'F.
SURVEILLANCE RE UIREMENTS 4.4.5.1 Steam Generator Sam le Selection and Ins ection -agach steam generator sha 1
be determine urging shut own 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 min>mum sample size, inspection result classification, and the corresponding action required 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.
Steam generator tubes shall be examined in accordance with the ASME Boiler and Pressure Vessel Code - Section XI-
"Inservice Inspection of Nuclear Power Plant Components" 1974 Edition i The tubes selected for each inservice inspection shall include at least 3X 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 experience in similar plants with similar water chemistry indicates critical areas to be inspected, then at least 50K of the tubes inspected shall be from these critical areas.
b.
The first inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:
l.
All nonplugged tubes that previously had detectable wall penetrations
(>20K), and Tubes in those areas where experience has indicated potential problems.
D.C.
COOK - UNIT 1
3/4 4-7
V
REACTOR COOLANT SYSTEM SURVEILLANCE RE UIREMENTS Continued) c.
The second and third inservice inspections may be less than a
full tube inspection by concentrating (selecting at least 50/
of the tubes to the inspected) the inspection on those areas of the tube sheet array and on those portions of the tubes where tubes with imperfections were previously found.
The results of each sample inspection shall be classified into one of the following three categories:
~Cate or C-1 Ins ection Results Less than 5C of'he total tubes inspected are degraded tubes and none of the inspected tubes are defective.
C-2 C-3 One or more tubes, but.not more than 1%
of'he total tubes inspected are defective, or between 5X and 10K of the total tubes inspected are degraded tubes.
More than 10'A of the total tubes inspected are degraded tubes or more than lX of the inspected tubes are defective.
C Note:
In all inspections, previously degraded tubes must exhibit significant
(>10%) further wall penetrations to be included in the above percentage calculations.
4.4.5.3 Ins ection Fre uencies - The above required inservice inspections of steam generator tubes sha 1
be performed at the following frequencies:
a ~
The first inservice inspection shall be performed after 6
Effective Full Power Months but within 24 calendar months of initial criticality.
Subsequent inservice inspections shall be performed at intervals of not less than 12 nor more than 24 calendar months after the previous inspection.
If two consecu-tive inspections following service under AVT conditions, not including the preservice inspection, result in all inspection results falling into the C-1 category 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.
D.C.
COOK - UNIT 1 3/4 4-8
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REACTOR COOLANT SYSTEM SURVEILLANCE RE UIREMENTS Continued b.
Co If the inservice inspection of a steam generator conducted in accordance with Table 4.4-2 requires a third sample inspection whose results fall in Category C-3, the inspection frequency shall be reduced to at least once per 20 months.
The reduction in inspection frequency shall apply until a subsequent inspection demonstrates that a third sample inspection is not required.
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.
1.
Primary-to-secondary tubes leaks (not including leaks originating from tube-to-tube sheet welds) in excess of the limits of Specification 3.4.6.2, 2.
A seismic occurrence greater than the Operating Basis Earthquake, 3.
A loss-of-coolant accident requiring actuation of the engineered safeguards, or 4.
A main steam line or feedwater line break.
4.4.5.4 Acce tance Criteria a ~
As used in this Specification:
~ff 2
pf 0
df f,f2 f0 or contour of a tube from that required by fabrication drawings or specifications.
Eddy-current testing indications below 20Ã of the nominal tube wall thickness, if detectable, may be considered as imperfections.
2.
~0d 2
2 -fd d
- pf0, g
wear or general corrosion occurring on either inside or outside of a tube.
P.
~0ddTb 0
f2 gfp f 2
202 of the nominal wall thickness caused by degradation.
4.
X De radation means the percentage of the tube wall t ickness a fected or removed by degradation.
D. C.
COOK - UNIT 1 3/4 4-9
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REACTOR COOLANT SYSTEM SURVEILLANCE RE UIREMENTS Continued 5.
Defect means an imperfection of such severity that it exceeds the plugging limit.
A tube containing a defect is defective.
Any tube which does not permit the passage of the eddy-current inspection probe shall be deemed a
defective tube.
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b.
6.
'Plu in Limit means the imperfection depth at or beyond w
hach the tube shall be removed from service because it may become unserviceable prior to the next inspection and is equal to 40K of the nominal tube wall thickness.
7.
Unserviceable describes the condition of a tube if it
'ee i
d i t i g
gt ii t it structural integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam lin'e or feedwater line break as specified in 4.4.5.3.c, above.
8.
Tube Ins ection means an inspection of the steam generator tu e rom the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg.
Theqsteam generator shall be determinedMSVSBE after completing the corresponding actions (plug all tubes exceeding the plugging limit and all tubes containing through-wall cracks) required by Table 4.4-2.
'.4.5.5
~Re orts a e b.
Following each inservice inspection of steam generator
- tubes, the number of tubes plugged in each steam generator shall be reported to the Comoission within 15 days.
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.
D.C.
COOK - UNIT 1 3/4 4-10
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REACTOR COOLANT SYSTEM SURVEILLANCE RE UIREMENTS Continued co 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.
l D.C.
COOK - UNIT 1
3/4 4-11
c TABLE 4.41 MINIMUMNUMBER OF STEAM GE!4ERATORS TO BE INSPECTED DURING INSERVICE INSPECTION Preservice Inspection No. of Steam Generators per Unit First Inservice Inspection No Two Three Four All Two One Yes Three Four Two Two Second 5 Subsequent Inservice Inspections One" One1 One2 One3 Table Notation:
3.
1.
The inservice inspection may be limited to one steam generator on a rotating schedule encompassing 3 N % of the tubes (where N is the number of steam generators in the plant) if the results of the first or previous inspections indicate that all steam generators are performing in a like manner.
Note that under some circumstances, the operating conditions in one or more steam generators may be found to be more severe than those in other steam generators.
Under such circum-stances the sample sequence shall be modified to inspect the most severe conditions.
2.
The other steam generator not inspected during the first inservice inspection shall be inspected.
The third and subsequent inspections. should follow the instructions described in 1 above.
steam generators not inspected during the first inservice inspections shall be inspected during the second and third inspections~
The fourth and subsequent inspections shall follow the instructions described in 1 above.
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TABLE 4.4-2 1ST SAMPLE INSPECTION STEAM GENERATOR TUBE INSPECTION 2ND SAMPLE fNSPECTION 3RD SAMPLE INSPECTION Sample Size A minimum of S Tubes per S. G.
Result C-1 C-2 C-3 Action Required None Plug defective tubes and inspect ad<litional 2S tubes in this S. G.
Inspect all tubes in this S. G., plug de.
fective tubes and inspect 2S tubes in each other S. G.
Prompt notification to NRC pursuant to specification 6.9.1 Result N/A C-1 C-2 C-3 AII other S. G.s are C-I Some S. G.s C-2 but no additional S. G. are C-3 Additional S. G. is C-3 Action Required N/A None Plug defective tubes and inspect additional 4S tubes in this S. G.
Perform action for C-3 result of first sample None Perform action for C-2 result of second sample Inspect all tubes in each S. G. and plug defective tubes.
Prompt notification to NRC pursuant to specification 6.9.1 Result N/A N/A C-2 C-3 N/A N/A N/A N/A Action Required N/A None Plug defective tubes Perform action for C-3 result of first sample N/A N/A N/A N/A 3
g Wlrere N is the nulnber of steam generators in the unit, and n is the number of steam generators inspected N
during an inspection