ML20083G219
| ML20083G219 | |
| Person / Time | |
|---|---|
| Site: | Millstone  (DPR-65-A-089, DPR-65-A-89) |
| Issue date: | 12/30/1983 |
| From: | John Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20083G220 | List: |
| References | |
| NUDOCS 8401110186 | |
| Download: ML20083G219 (10) | |
Text
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UMITED STAYES g
NUCLEAR REGULATORY COMMISSION 5
- j WASHINGTON, D. C. 20555
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NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 89 License No. DPR-65 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee) dated June 3, 1983 as supplemented on August 18 and November 17, 1983, complies with the standards and require-ments 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 tFe Commission; C.
There is reasonable assurance (1) that the activities authorized 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 Comission's regulations and all applicable requirements have been satisfied.
8401110186 831230 PDRADOCK05000g P
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-65 is hereby amended to read as follows:
(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 Specifica-tions.
3.
This license amendment is effective on the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION p'
James R. Miller, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 30, 1983
' ATTACHMENT TO LICENSE AMENDMENT N0. 89 FACILITY OPERATING LICENSE N0. DPR-65 DOCKET NO. 50-336 Remove and replace the'following pages of the Appendix A Technical Specifica-tions with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines. indicating the area of change. The corre-sponding overleaf pages are provided to maintain document completeness.
Remove Insert 5/4 4-7a.
3/4 4-7a 3/4 4-7b 3/4 4-7b 3/4 4-7f 3/4 4-7f
'B 3/4 4-2a B 3/4 4-2a
a REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.1.3 Inspection Frequencies - The above required inservice inspections of steam generator tubes shall be performed at the following frequencies:
The first inservice inspection shall be performed after 6 a.
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 consecutive inspections following service under AVT conditions, not including the preservice inspection, result in all inspec-tion results falling into the C-1 category or if two consecu-tive inspections demonstrate that previously observed degrada-tion has not continued and no additional degradation has occurred, the inspection interval may be extended to a maximum of once per 40 months.
b.
If the results of the inservice inspection of a steam generator conducted in accordance with Table 4.4-6 at 40 month intervals fall into 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 inspec-tions satisfy the criteria of Specification 4.4.5.1.3.a; the interval may then be extended to a maximum of once per 40
-months.
Additional, unscheduled inservice inspections shall be per. formed c.
'on each steam generator in accordance with the first sample inspection specified in Table 4.4-6 during the shutdown subse-quent 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.*
l 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.
- For the outage commencing on March 1,1983 only, the inservice inspection requirements of Category C-1 of Table 4.4-6 are deferred to the 1983
-refueling outage.
I MILLSTONE - UNIT 2 3/4 4-7 Amendment No. 22, 3//, 33 i
REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.1.4 Acceptance Criteria a.
As used in this 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 indications 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 be 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 or sleeve containing a defect is l
defective.
6.
Plugging Limit means the imperfection depth at or beyond which.
the tube or sleeve shall be repaired because it may become I
unserviceable prior to the next inspection and is equal to 40%
of the nominal tube wall thickness for tubes.*
7.
Unserviceable describes the condition of a tube 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 4.4.5.1.3.c, above.
8.
Tube Inspection means an inspection of the steam generator tube from the point of entry (hot leg side) completely around the U - Bend to the top support of the cold leg.
b.
The steam generator shall be detennined OPERABLE after completing the corresponding actions (plug or sleeve all tubes exceeding the l
plugging limit and plug all defective sleeves) required by Table 4.4-6.
MILLSTONE - UNIT 2 3/4 4-7a Amendment No. 22, 37, EZ, 89
- The plugging limit for sleeves will be determined prior to next refueling outage.
REACTOR C0OLANT SYSTEM SURVEILLANCE. REQUIREMENTS (Continued) 4.4.5.1.5 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 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.
c.
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.
MILLSTONE - UNIT 2 3/4 4-7b Amendment No. 72, 37, EZ, 89
This page intentionally lef t blank.
MILLSTONE - UNIT 2 3/4 4-7c Amendment No. 37,52
t 2
p
- TABLE.4.44 GY STEAM GENERATOR TUBE INSPECTION r"
' 1ST SAMPLE INSPECTION 2ND SAMPLE INSPECTION 3RD SAMPLE INSPECTION c-2
. Samp'e Size Result.
Action Required -
. Result.
Action Required Result Action Required.
' -i to A minimum of C-1 None N/A N/A
.N/A
.N/A S Tubes per S. G.
Repair defective C-2 tubes and inspect..
C-1
- Nor's N/A N/A
'l additional 25 C-1 None Repair defective
-tubes in this C-2 S.G.*
tubes and inspect C-2 Repairdefecthetubes*
additional 45 Perform action for tubes in this s.G.*
C-3 C-3 result of first ca s
sample A
A Perform action for O
C-3 C-3 result of first N/A N/A sample C-3 Inspect all tubes All other in this S.G., repair S. G.s are None N/A N/A defective tubes and C-1 inspect 25 tubes in each other S.G.*
Some S. G.s Perform action for N/A N/A C-2 but no C-2 result of sec.ond additional sample Prompt notification S. G. are
- s to NRC pursuant C-3 to specification Additional Inspect all tubes -
6.9.1 S. G. is C-3 in each S.G. and
- 3r+
repair defective tubes.* Prompt N/A N/A zo notification to NRC pursuant to spect-wa fication 6.9.1.
hl
.N Where N is the number of steam generators in the unit. and n is the number of steam generators inspected S=3 during an inspection
-e n-w
- ae
- Repair of defective tubes shall be~ limited to plugging with the exception of those
,g tubes which may be. sleeved. Tubes with defective sleeves shall be plugged.
-~
REACTOR COOLANT SYSTEM 3/4.4.6 REACTOR C0OLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.6.1 The following Reactor Coolant System leakage detection systems shall be OPERABLE:
a.
A containment atmosphere particulate radioactivity monitoring
- system, b.
The containment sump level monitoring system, and c.
A containment atmosphere gaseous radioactivity monitoring system.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
a.
With one of the above radioactivity monitoring leakage detection systems inoperable, operations may continue for up to 30 days provided:
1.
The other two above required leakage detection systems are OPERABLE, and 2.
Appropriate grab samples are obtained and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; otherwise, be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
b.
With the containment sump level monitoring system inoperable, restore the inoperable system to OPERABLE status within 7 days or be in COLD S:iUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.4.6.1 The leakage detection systems shall be demonstrated OPERABLE by:
a.
Containment atmosphere gaseous and particulate monitoring systems-performance of CHANNEL CHECK, CHANNEL CALIBRATION and CRANNEL FUNCTIONAL TEST at the frequencies specified in Table 4.3-3, and b.
Containment sump level monitoring system-performance of CHANNEL CALIBRATION TEST at least once per 18 months.
MILLSTONE - UNIT 2 3/44-8
REACTOR COOLANT SYSTEM BASES 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 correc-tive 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 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 = 0.5 GPM, per steamgenerator). 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 0.5 gallon per minute can readily be detected by radiation monitors of steam generator blow-down. Leakage in excess of this limit will require plant shutdot:n and an unscheduled inspection, during which the leaking tubes will be located and pl ugged.
Wastage-type defects are unlikely with proper chemistry treatment of the secondary coolant. However, even if a defect should develop in service, it will be fnund during scheduled inservice steam generator tube examinations.
Plugging or sleeving will be required for all tubes with imperfections exceed-ing the plugging limit of 40% of tne tube nominal wall thickness. Sleeving repair will be limited to those steam generator tubes with a defect between the tube sheet and the first eggcrate support. Tubes containing sleeves with imperfections exceeding the plugging limit will be plugged.
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.
MILLSTONE - UNIT 2 B 3/4 4-2a Amendment No. 22, 37, E2, $6,89