ML20207J446
| ML20207J446 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 12/19/1986 |
| From: | Thadani A Office of Nuclear Reactor Regulation |
| To: | Baltimore Gas & Electric Co (BGE) |
| Shared Package | |
| ML20207J450 | List: |
| References | |
| DPR-53-A-125, DPR-69-A-106 NUDOCS 8701080456 | |
| Download: ML20207J446 (28) | |
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NUCLEAR REGULATORY COMMISSION
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WASHINGTON. D. C. 20555
't, *... +,e BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.125 Licens'e No. DPR-53 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Baltimore Gas & Electric Company (the licensee) dated July 31, 1986, as supplemented by the November 5, 1986 submittal, 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; 8.
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 will be conducted in compliance with the Commission's regulations; 0.
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 1s in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
1
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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. DPR-53 is hereby i
amended to read as follows:
j (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.125, are hereby incorporated in the 5
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.
1 FOR THE NUCLEAR REGULATORY COMMISSION
, hbbt 7f'U' Asho "C.' Thadani, Director PWR roject Directorate #8 i
Division of PWR Licensing-B
Attachment:
Changes to the Technical Specifications Date of Issuance: December 19, 1986 i
i s
ATTACHMENT TO LICENSE AMENDMENT NO. 125 FACILTIY OPERATING LICENSE NO. OPR-53 DOCKET NO. 50-317 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change. The corresponding overleaf pages are provided to maintain document completeness.
Remove Page's Insert Pages 3/4 4-28 3/4 4-28 3/4 7-25 3/4 7-25 3/4 7-26a 3/4 7-26a 3/4 7-26b 3/4 7-26b 3/4 7-27 through 3/4 7-62 inclusive B 3/4 7-5 B 3/4 7-5 6-20 6-20
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REACTOR COOLANT SYSTEM 3/4.4.10 STRUCTURAL INTEGRITY ASME CODE CLASS 1, 2 AND 3 COMPONENTS LIMITING CONDITION FOR OPERATION 3.4.10.1 The structural integrity of ASME Code Class 1, 2 and 3 com-ponents shall be maintained in accordance with Specification 4.4.10.1.
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APPLICABILITY:- AL'L MODES.
ACTION:
a.
With the structural integrity of any ASME Code Class 1 com-ponent(s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature more than 50'F above the minimum temperature required by NDT considera-tions.
b.
With the structural integrity of any ASME Code Class 2 com-ponent(s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature above 200 F.
c.
With the structural integrity of any ASME Code Class 3 com-ponent(s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) from service.
d.
The provisions of Specification'3.0.4 are not applicable.
SURVEILLANCE RE0VIREMENTS 4.4.10.1.1 The structural integrity of ASME Code Class 1, 2 and 3 components shall be demonstrated:
a.
Per the requirements of Specification 4.0.5, and b.
Per the requirements of the augmented inservice inspection program specified in Specification 4.4.10.1.2.
CALVERT CLIFFS - UNIT 1 3/4 4-27
1 REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)
In addition to the requirements of Specification 4.0.5, each Reactor Coolant Pump flpheel shall be inspected per the recomendations of Regulatory Position C.4.b of Regulatory Guide 1.14. Revision 1 August I
1975.*
4.4.10.1.2 Augmented Inservice Inspection Program for Main Steam I
and Main Feedwater Piping - The unencapsulated welds greater than 4 inches in nominal diameter in the main steam and main feedwater piping runs located outside the containment and traversing saLfety related areas or located in compartments adjoining safety related areas shall be inspected per the following augmented inservice in-spection program using the applicable rules, acceptance criteria, and repair procedures of the ASME Boiler and Pressure Vessel Code,
),
Section XI,1974 Edition and Addenda through Summer 1975, for Class 4
2 components.
l a.
System integrity and baseline data shall be established by performing a 100% volumetric examination of each weld-prior to exceeding 18 months of operation.
)
b.
Each weld shall be examined in accordance with the above ASME Code requirements, except that 100% of the welds shall be examined, cumulatively, during each 10 year in-spection interval. The welds to be examined during each inspection period shall be selected to provide a repre-sentative sample of the conditions of the welds.
If these examinations reveal unacceptable structural defects in one or more welds, an additional 1/3 of the welds shall be examined and the inspection schedule for the repaired welds shall revert back to the first 10 year inspection program.
If additional unacceptable defects are detected in the second sampling, the remainder of the welds shall also be inspected.
- Reactor coolant pump flywheel inspections for the first inservice inspection interval may be completed by June 1990 in conjunction with the reactor coolant pump motor overhaul program.
CALVERT CLIFFS - UNIT 1 3/4 4-28 Amendment No. 7),125
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PLANT SYSTEMS 3/4.7.8 SNUBBERS LIMITING CONDITION FOR OPERATION l
3.7.8.1 All safety related snubbers shall be OPERABLE.
1 APPLICABILITY: MODES 1, 2, 3 and 4.
(l10 DES 5 and 6 for snubbers located on systems required OPERABLE in those MODES.
ACTION:
With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber (s) to OPERABLE status, and perform an engineering evalua-tion
- per Specification 4.7.8.b and.c on the supporting component or declare the supported system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE REQUIREMENTS 4.7.8.1 Each snubber shall be demonstrated OPERABLE by perfomance of the following augmented inservice inspection program ar.d the requirements of Specification 4.0.5.
As used in this Specification, type of snubber shall mean snubbers of the same design and manufacturer, irrespective,of capacity.
a.
Visual inspections Visual inspections shall be performed in accordance with the following schedule:
No. Inoperable Snubbers of Subsequent Visual **
Each Type per Inspection Pericd, Inspection Period #
0 18 months + 25%
1 12 months T 25%
2 6 months T 25%
3, 4 124 days 1 25%
5,6,7 62 days 1 25%
8 or more 31 days 1 25%
The snubbers may be further categorized into two groups: Those accessible and those inaccessible during reactor operation.
Each group may be inspected independently in accordance with the above schedule.
1 Safety related snubbers include those snubbers installed on safety related systems and snubbers on non-safety related systems if their failure or the failure of the system on which they are installed would have an adverse effect on any safety related system.
A documented, visual inspection shall be sufficient to meet the requirements for an engineering evaluation.
Additional analyses, as needed, shall be completed in a reasonable period of time.
- The inspection interval shall not be lengthened more than two steps at a time.
- The provisions of Specification 4.0.2 are not applicable.
CALVERT CLIFFS - UNIT 1 3/4 7-25 Amendment No. $4.JJB,125
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.
Visual Inspection Acceptance Criteria Visual inspections shall verify (1) that there are no visible indica-tions of damage or impaired OPERABILITY, and (2) that the snubber installation exhibits no visual indications of detachment from foundations or supporting structures. Snubbers which appear inoper-able as a result of visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection interval, providing that (1) the cause of the rejection is clearly established and r medied for th3t particular snubber and for other snubbers that may be generically susceptible; and/or (2) the affected snubber is functionally tested in the as found condition and determined OPERABLE per Specification 4.7.8.d, as applicable. When the fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be determined inoperable unless it can be determined OPERABLE via functional testing for the purpose of establishing the next visual inspection interval.
For the snubber (s) found inoperable, an engineering evaluation shall be performed on the component (s) which are supported by the snubber (s).
The scope of this engineering evaluation shall be consistent with the licensee's engineering judgment and may be limited to a visual inspection of the supported component (s).
The purpose of this engineering evaluation shall be to determine if the component (s) supported by the snubber (s) were adversely affected by the inoperability of the snubber (s) in order to ensure that the supported component remains capable of meeting the designed service.
c.
Functional Tests At least once per 18 months during shutdown, a representative sample of 10% of each type of snubbers in use in the plant shall l
be functionally tested either in place or in a bench test.* Fcr each snubber that does not meet the functional test acceptance criteria of Specification 4.7.8.d, an additional 5% of that type l
snubber shall be functionally tested until no more failures are found or until all snubbers of that type have been functionally l
tested.
- The Steam Generator snubbers 1-63-13 through 1-63-28 need not be functionally tested until the refueling outage following June 30, 1985.
CALVERT CLIFFS - UNIT 1 3/4 7-26 Amendment No. JE,6f,79),118
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
Snubbers identified as "Especially Difficult to Remove" dr in "High Exposure Zones" shall also be included in the representative sample.*
In addition to the regular sample, snubbers which failed the previous functional test shall be retested during the next test period.
If a spare snubber has been installed in place of a failed snubber, then both the failed snubber (if it is repaired and installed in another position) and the spare snubber shall be retested during the next test
~1 period; : Failure of these snubbers shall not entail functional testing
'of additional snubbers.
If any snubber selected for functional testing either fails to lock up l
or fails to move, i.e., frozen in place, the cause will be evaluated i
and if caused by manufacturer or design deficiency all generically susceptible snubbers of the same design subject to the same defect shall be functionally tested. This testing requirement shall be t
independent of the requirements stated above for snubbers not meeting the functional test acceptance criteria.
For the snubber (s) found inoperable, an engineering evaluation shall be performed on the component (s) which are supported by the snubber (s).
The scope of this engineering evaluation shall be consistent with the licensee's engineering judgment and may be limited to a visual inspec-i tion of the supported component (s). The purpose of this engineering evaluation shall be to determine if the component (s) supported by the snubber (s) were adversely affected by the inoperability of the snubber (s) in order to ensure that the supported component remains capable of meeting the designed service, d.
Hydraulic Snubbers Functional Test Acceptance Criteria The hydraulic snubber functional test shall verify that:
1.
Activation (restraining. action) is achieved within the specified range of velocity or acceleration in both tension and compression.
2.
Snubber bleed, or release rate, where required, is within the specified range in compression or tension. For snubbers specifically required to not displace under continuous load, the ability of the snubber to withstand load without displacement shall be. verified.
- Permanent or other exemptions from functional testing for individual snubbers in these categories may be granted by the Commission only if a justifiable basis for exemption is presented and/or snubber life destructive testing was performed to qualify snubber operability for all design conditions at either the completion of their fabrication or at a subsequent date.
'CALVERT CLIFFS - UNIT 1 3/4 7-26a Amendment No./g/,125
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PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) e.
Snubber Service Life Monitoring l
A record of the service life of each snubber, the date at which the designated service life commences and the installation and maintenance records on which the designated service life is based shall be main-tained as required by Specification 6.10.2.m.
At 1 east once per 18 months, the installation and maintenance records 2
for each, safety related snubber shall be reviewed to verify that the l
indicated service life has not been exceeded or will not be exceedeo prior to the next scheduled snubber service life review.*
If the l
indicated service life will be exceeded prior to the next scheduled snubber service life review, the snubber service life shall be re-evaluated or the snubber shall be replaced or reconditioned so as to extend its service life beyond the date of the next scheduled service life review. This reevaluation, replacement, or reconditioning shall be indicated in the records.
(
The provisions of Specification 4.0.2 are applicable.
CALVERT CLIFFS - UNIT 1 3/4 7-26b Amendment No. $4,Jp),125 f
PAGES 3/4 7-27 THROUGH 3/4 7-62 WERE DELETED BY AMENDMENT N0.
l CALVERT CLIFFS - UNIT 1 3/47-27 through 3/4 7-62 Amendment No. 125
PLANT SYSTEMS
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BASES environment. The operation of this system and the resultant effects on offsite dosage calculations was assumed in the accident analyses.
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3/4.7.8 SNUBBERS All safety related snubbers are required OPERABLE to ensure that the structural l
integrity of the reactor coolant system and all other safety related systems is maintained during and following a seismic or other event initiating dynamic loads.
Snubbers excluded from this inspection program are those installed on non-safety related systems and then only if their failure or failure of the system on which they are installed,would have no adverse effect on any safety-related system.
The visual inspection frequency is based upon maintaining a constant level of f
snubber protection to systems. Therefore, the required inspection interval varies inversely with the observed snubber failures and is detennined by the number of inoperable snubbers of each type
- found during an inspection.
Inspections performed before that interval has elapsed may be used as a new reference point to determine i
the next inspection.
However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 25%) may
{
not be used to lengthen the required inspection interval. Any inspection whose l
results require a shorter inspection interval will override the previous schedule.
I e
i When the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may be generically susceptible, and verified by inservice functional testing, that snubber may be exempted from are (1) of a specific make or model, (2)y susceptible snubbers are those whichof the s being counted as inoperable. Genericall q
located or exposed to the same environmental conditions such as temperature, radiation, and vibration. These characteristics of the snubber installation shall be evaluated to determine if further functional testing of similar snubber installations is warranted.
When a snubber is found inoperable, an engineering evaluation is performed, in addition to the determination of the snubber mode of failure, in order to deter-mine if any safety-related component or system has been adversely affected by the inoperability of the snubber. The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or degrada-tion on the supported component or system.
To provide assurance of snubber functional reliability, a representative sample i
of the installed snubbers of each type
- will be functionally tested during plant shutdowns at 18 month intervals. Observed failures of these sample snubbers i
shall require functional testing of additional units.
The service life of a snubber is evaluated via manufacturer input and information through consideration of the snubber service conditions and associated installa-tion and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature area, etc.... ). The requirement to monitor the snubber service life is included to ensure that the
- Small bore Q8") and large bore (>8") hydraulic snubbers are examples of different types of snubbers.
j CALVERT CLIFFS - UNIT.1 B 3/4 7-5 Amendment No. H,JJ$,125 H
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PLANT S'YSTEMS BASES snubbers periodically undergo a performance. evaluation in view of their age and operating conditions. The service life program is designed to uniquely reflect the conditions at Calvert Cliffs. The criteria for evaluating service life shall be determined, and documented, by the licensee. Records will provide statistical bases for future consideration of snubber service life. The requirements for the maintenance of records and the snubber service life review are not intended to affect plant operation.
3/4.7.9 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits
- for plutonium. This limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values.
3/4.7.10 WATERTIGHT D0 ORS This specification is provided to ensure the protection of safety related equip-ment from the effects of water or steam escaping from ruptured pipes or components in adjoining rooms.
3/4.7.11 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire
.l suppression capability is available to confine and extinguish fires occurring in any portion of the facility where safety related equipment is located. The fire suppression system consists of the water system, spray and/or sprinklers Halon and fire hose stations. The collective capability of the fire suppres-sion systems is adequate to minimize potential damage to safety related equip-ment and is a major element in the facility fire protection program.
In the event that portions of the fire suppression systems are inoperable, alternate backup fire fighting equipment is required to be made available in the affected areas until the inoperable equipment is restored to service.
Where a continuous fire watch is required. in lieu of fire protection equipment and habitability due to heat or radiation is a concern, the fire watch should be stationed in a habitable area as close as possible to the inoperable equip-ment.
In the event the fire suppression water system becomes inoperable, immediate corrective measures must be taken since this system provides the major fire suppression capability of the plant. The requirement for a twenty-four hour report to the Commission provides for prompt evaluation of the acceptability of the corrective measures to provide adequate fire suppression capability for the continued protection of the nuclear plant.
CALVERT CLIFFS - UNIT 1 B 3/4 7-6 Amendment No. 26, 57, ? -f
ADMINISTRATIVE CONTROLS 6.10 RECORD RETENTION 6.10.1 The following records shall be retained for at least five years:
a.
Records and logs of facility operation covering time interval at each power level.
b.
Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.
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c.
All REPORTABLE EVENTS.
d.
Records of surveillance activities, inspections and calibrations required by these Technical Specifications, e.
Records of reactor tests and experiments.
f.
Records of changes made to Operating Procedures.
g.
Records of radioactive shipments.
h.
Records of sealed source and fission detector leak tests and results.
i.
Records of annual physical inventory of all sealed source material of record.
6.10.2 The following records shall be retained for the duration of the Facility Operating License:
a.
Records and drawing changes reflecting facility design modifi-cations made to systems and equipment described in the Final Safety Analysis Report.
b.
Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
c.
Records of facility radiation and contamination surveys.
CALVERT CLIFFS - UNIT 1 6-19
. Amendment No. 29, 94 i
i
ADMINISTRATIVE CONTROLS d.
Records of radiation exposure for all individuals entering radiation control areas.
e.
Records of gaseous and liquid radioactive material released to the environs.
f.
Records of transient or operational cycles for those facility components identified in Table 5.7-1.
g.
Records of training and qualificaticn for current members of the plant staff.
h.
Records of in-service inspections performed pursuant to these Technical Specifications.
- i. Records of Quality Assurance activities identified in the NRC approved QA Manual as lifetime records.
j.
Records of reviews performed for changes made to procedures or equip-ment or reviews of tests and experiments pursuant to 10 CFR 50.59.
i k.
Records of meetings of the POSRC and the OSSRC.
1.
Records of Environmental Qualification which are covered under the l
provisions of paragraph 6.13.
m.
Records of the service lives of all safety related snubbers including l
the date at which the service life commences and associated installation and maintenance records.
i 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared c.onsistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adher'ed to for all operations involving personnel. radiation exposure.
6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR Part 20:
A high radiation area in which the intensity of radiation is greater j
i -
a.
than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a High Radiation Area and entrance thereto shall be controlled by issuance of a Special or Radiation Work Permit and any individual or group of individuals permitted to enter such-I areas shall be provided with a radiation monitoring device which continuously indicates the radiation dose rate in the area.
I CALVERT CLIFFS - UNIT 1 6-20 Amendment No. $$.125
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u UNITED STATES 8"
NUCLEAR REGULATORY COMMISSION E
WASHINGTON. D. C. 20555 gh BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.106 Licens'e No. DPR-69 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Baltimore Gas & Electric Company (the licensee) dated July 31, 1986, as supplemented by the November 5, 1986 submittal, 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; 8.
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 witnout 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.
~ -
~2-2.
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-69 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.106, are hereby incorporated in the license...The licensee shall operate the facility in accordance with
-the Tech'ical Specifications.
n 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION bOL Ashok C 'Thadani, Director PWR Project Directorate #8 Division of PWR Licensing-B
Attachment:
Changes to the Technical Specifications Date of Issuance: December 19, 1986
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f l
l ATTACHMENT TO LICENSE AMENDMENT NO.106 FACILTIY OPERATING LICENSE NO. DPR-69 DOCKET NO. 50-318 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
The corresponding overleaf pages are provided to maintain document completeness.
1 Remove Pages Insert Pages 3/4 4-29 3/4 4-29 3/4 7-25 3/4 7-25 3/4 7-26a 3/4 7-26a 3/4 7-26b 3/4 7-26b 3/4 7-27 through 3/4 7-54 inclusive B 3/4 7-5 B 3/4 7-5 j
6-20 6-20 5
1 1
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a t
i
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REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)
In addition to the requirements of Specification 4.0.5, each Reactor Coolant Pump flywheel shall be inspected per the recomendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1 August I
1975.*
4.4.10.1.2 Augmented Inservice Inspection Program for Main Steam and Main Feedwater Piping - The unencapsulated welds greater than 4 inches in nominal diameter in the main steam and main feedwater piping runs located outside the containment and traversing safety related areas or located in compartments adjoining safety related areas shall be inspected per the following augmented inservice in-spection program using the applicable rules, acceptance criteria, and repair procedures of the ASME Boiler and Pressure Vessel Code,Section XI,1974 Edition and Addenda through Summer 1975, for Class 2 components.
System integrity and baseline data shall be established by a.
performing a 100% volumetric examination of each weld prior to exceeding 18 months of operation.
b.
Each weld shall be examined in accordance with the above ASME Code requirements, except that 100% of the welds shall be examined, cumulatively, during each 10 year in-spection interval. The welds to be examined during each inspection period shall be selected to provide a repre-sentative sample of the conditions of the welds.
If these examinations reveal unacceptable structural defects in one or more welds, an additional 1/3 of the welds shall be examined and the inspection schedule for the repaired welds shall revert back to the first 10 year inspection program.
If additional unacceptable defects are detected in the second sampling, the remainder of the welds shall also be inspected.
- Reactor coolant pump flywheel inspections for the first inservice inspection interval may be completed by June 1991 in conjunction with the reactor coolant pump motor overhaul program.
CALVERT CLIFFS - UNIT 2 3/4 4-29 AmendmentNo.pp,106
._.2 REACTOR COOLANT SYSTEM CORE BARREL MOVEMENT LIMITING CONDITION FOR OPERATION 3.4.11 Core barrel movement shall be limited to less than the Amplitude Probability Distribution (APD) and Spectral Analysis (SA) Alert Levels for the applicable THERMAL POWER level.
APPLICABILIT : " H0DE 1.
ACTION:
a.
With the APD and/or SA exceeding their applicable Alert Levels, POWER OPERATION may proceed provided the following actions are taken:
1.
APD shall be measured and processed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 2.
SA shall be measured at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and shall be processed at least once per 7 days, and 3.
A Special Report, identifying the cause(s) for exceeding the applicable Alert Level, shall be prepared and sub-mitted to the Commission pursuant to Specification 6.9.2 within 30 days of detection.
l b.
With the APD and/or SA exceeding their applicable Action Levels, measure and process APD and SA data within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to determine if the core barrel motion is exceeding its limits. With the core barrel motion exceeding its limits, reduce the core barrel motion to within its Action Levels within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in HOT STANDBY within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
CALVERT CLIFFS - UNIT 2 3/4 4-30 Amendment No. 39
PLANT SYSTEMS 3/4.7.8 SNUBBERS LIMITING CONDITION FOR OPERATION l
3.7.8.1 All safety related snubbers shall be OPERABLE.
'l APPLICABILITY: liODES 1, 2, 3 and 4.
(MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES.)
ACTION:
With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber (s) to OPERABLE status, and perform an engineering evalua-tion
- per Specification 4.7.8.b and c on the supported comp ~onent or declare the supported system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE REQUIREf1ENTS 4.7.8.1 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.
As used in this Specification, type of snubber shall mean snubbers of the same design and manufacturer, irrespectivA of capacity.
a.
Visual Inspections Visual inspections shall be perfonned in accordance with the j
following schedule:
No. Inoperable Snubbers of Subsequent Visual **
Each Type per Inspection Period Inspection Period #
0 18 months + 25%
1 12 months T 25%
2 6 months T 25%
3, 4 124 days 1 25%
5,6,7 62 days 1 25%
8 or more 31 days 1 25%
The snubbers may be further categorized into two groups: Those accessible and those inaccessible during reactor operation. Each group may be inspected independently in accordance with the above schedule.
1 Safety related snubbers include those snubbers installed on safety related systems and snubbers on non-safety related systems if their failure or the failure of the system on which they are installed would have an adverse effect on any safety related system.
A documented, visual inspection shall be sufficient to meet the requirements for an engineering evaluation. Additional analyses, as needed, shall be completed in a reasonable period of time.
- The inspection interval shall not be lengthened more than two steps at a time.
- The provisions of Specification 4.0.2 are not applicable.
CALVERT CLIFFS - UNIT 2 3/4 7-25 Amendment No. J0,H,J00, 106 1
- 1 PLANT SYSTEMS l
SURVEILLANCE REQUIREMENTS (Continued) b.
Visual Inspection Acceptance Criteria Visual inspections shall verify (1) that there are no visible indica-tions of damage or impaired OPERABILITY, and (2) that the snubber installation exhibits no visual indications of detachment from foundations or supporting structures. Snubbers which appear inoper-able as a result of visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection interval, pr,oviding that (1) the.cause of the rejection is clearly established and remedied for that particular snubber and for.other snubbers that may be generically susceptible; and/or (2) the affected snubber is functionally tested in the as found condition and determined OPERABLE per Specification 4.7.8.d as applicable. When the fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be determined inoperable unless it can be determined OPERABLE via functional testing for the purpose of establishing the next visual inspection interval.
For the snubber (s) found inoperable, an engineering evaluation shall be performed on the component (s) which are supported by the snubber (s). The scope of this engineering evaluation shall be consistent with the licensee's engineering judgment and may be limited to a visual inspection of the supported component (s).
The purpose of this engineering evaluation shall be to determine if the component (s) supported by the snubber (s) were adversely affected by the inoperability of the snubber (s) in order to ensure that the supported component remains capable of meeting the designed service.
c.
Functional Tests _
At least once per 18 months during shutdown, a representative sample of 10% of each type of snubbers in use in the plant shall l
be functionally tested either in place or in a bench test.* For each snubber that does not meet the functional test acceptance criteria of Specification 4.7.8.d, an additional 5% of that type j
snubber shall be functionally tested until no more failures are found or until all snubbers of that type have been functionally l
tested.
- The Steam Generator snubbers 2-63-11 through 2-63-26 need not be functionally tested until the refueling outage following June 30, 1985.
0 CALVERT CLIFFS - UNIT 2 3/4 7-26 Amendment No.J9,3S,$$,73,10
q PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
Snubbers identified as "Especially Difficult to Remove" or in "High Radiation Zones" shall also be included in the representative sample.*
In addition to the regular sample, snubbers which failed the previous functional test shall be retested during the next test period. If a spare snubber has been installed in place of a failed snubber, then both the failed snubber (if it is repaired and installed in another position) and the spare snubber shall be retested during the next test Failure of these snubbers shall not entail functional testing period.. ~
of additional snubbers.
If any snubber selected for functional testing either fails to lock up or fails to move, i.e., frozen in place, the cause will be evaluated and if caused by manufacturer or design deficiency all generically susceptible snubbers of the same design subject to the same defect shall be functionally tested. This testing requirement shall be independent of the requirements stated above for snubbers not meeting the functional test acceptance criteria.
For the snubber (s) found inoperable, an engineering evaluation shall be performed on the component (s) which are supported by the snubber (s).
i The scope of this engineering evaluation shall be consistent with the licensee's engineering judgment and may be limited to a visual inspec-tion of the supported component (s). The purpose of this engineering -
evaluation shall be to determine if the component (s) supported by the snubber (s) were adversely affected by the inoperability of the snubber (s) in order to ensure that the supported component remains capable of meeting the designed service.
d.
Hydraulic Snubbers Functional Test Acceptance Criteria The hydraulic snubber functional test shall verify that:
1.
Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.
2.
Snubber bleed, or release rate, where required, is within the specified range in compression or tension.
For snubbers specifically required to not displace under continuo'us load, the ability of the snubber to withstand load without displacement shall be verified.
- Permanent or other exemptions from functional testing for individual snubbers in these categories may be granted by the Commission only if a justifiable basis for exemption is presented and/or snubber life destructive testing was performed to qualify snubber operability for all design conditions at either the completion of their fabrication or at a subsequent date.
CALVERT CLIFFS - UNIT 2 3/4 7-26a Amendment No. M, /$',106
)
..a-.~.....
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) e.
Snubber Service Life Monitoring l
A record of the service life of each snubber, the date at which the designated service life commences and the installation and maintenance records on which the designated service life is based shall be main-tained as required by Specification 6.10.2.m.
At least once per 18 months, the installation and maintenance records
' for each safety related snubber shall be reviewed tp verify that the l
indicated service life has not been exceeded or will not be exceeded prior to the next scheduled snubber service life review.* If the
~
indicated service life will be exceeded prior to the next scheduled snubber service life review, the snubber service life shall be re-evaluated or the snubber shall be replaced or reconditioned so as to extend its service life beyond the date of the next scheduled service life review. This reevaluation, replacement or reconditioning shall be indicated in the records.
4
- The provisions of Specification 4.0.2 are applicable.
CALVERT CLIFFS - UNIT 2 3/4 7-26b Amendment No. 35,$6,73,106
u.
o PAGES 3/4 7-27 THROUGH 3/4 7-54 DELETED BY AMENDMENT NO.
4 I
).
i 2,
CALVERT CLIFFS - UNIT 2 3/4 7-27 through 3/4 7-54 Amendment No.106 a
W
~T--'MF-*s'-1-T-wg_,9
PLANT SYSTEMS BASES environment. The operation of this system and the resultant effects on offsite dosage calculations was assumed in the accident analyses.
3/4.7.8 SNUBBERS All safety related snubbers are required OPERABLE to ensure that the structural l
integrity of the reactor coolant system and all other safety related systems is maintained during and following a seismic or other event initiating dynamic loads.
Snubbers excluded from this inspection program are those installed on non-safety related systems and then only if their failure or failure of the system on which they are installed would have no adverse effect on any safety-related system.
The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems. Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers of each type
- found during an inspection.
Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection. However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 25%) may not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inspection interval will override the prcvious schedule.
When the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may be generically susceptible, and verified by inservice functional testing, that snubber may be exempted from being counted as inoperable. Genericall are (1) of a specific make or model, (2)y susceptible snubbers are those whichof the s located or exposed to the same environmental conditions such as temperature, radiation, and vibration. These characteristics of the snubber installation shall be evaluated to determine if further functional testing of similar snubber installations is warranted.
When a snubber is found inoperable, an engfrieering evaluation is performed, in addition to the determination of the snubber mode of failure, in order to deter-mine if any safety-related component or system has been adversely affected by the inoperability of the snubber. The engince' ring evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or degrada-tion on the supported component or system.
To provide assurance of snubber functional reliability, a representative sample of the installed snubbers of each type
- will be functionally tested during plant shutdowns at 18 month intervals. Observed failures of these sample snubbers shall require functional testing of additional units.
i The service life of a snubber is evaluated via manufacturer input and information through consideration of the snubber service conditions and associated installa-tion and maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature area, etc....).
The requirement to monitor the snubber service life is included to ensure that the
- Small bore (<8") and large bore (>8") hydraulic snubbers are examples of different types of snubbers.
CALVERT CLIFFS - UNIT' 2 B 3/4 7-5 Amendment No. O, N d, 106
)
.j PLANT SYSTEMS BASES snubbers periodically undergo a performance evaluation in view of their age and operating conditions. The service life program is designed to uniquely reflect the conditions at Calvert Cliffs. The criteria for evaluating service life shall be determined, and documented, by the licensee. Records will provide statistical bases for future consideration of snubber service life. The requirements for the maintenance of records and the snubber service life review are not intended to affect plant operation.
3/4.7.9 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits-for plutonium. This limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values.
o 3/4.7.10 WATERTIGHT DOORS This specification is provided to ensure the protection of safety related equip-ment from the effects of water or steam escaping from ruptured pipes or components in adjoining rooms.
6 3/4.7.11 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring in any portion of the facility where safety related equipment is located. The fire suppression system consists of the water system, spray and/or sprinklers, Halon and fire hose stations. The collective capability of the fire suppres-sion systems is adequate to minimize potential damage to safety related equip-ment and is a major element in the facility fire protection program.
In the event that portions of the fire suppression systems are inoperable, alternate backup fire fighting equipment is required to be made available in the affected areas until the inoperable equipment is restored to service.
Where a continuous fire watch is required, in lieu of fire protection equipment and habitability due to heat or radiation is a concern, the fire watch should be stationed in a habitable area as close as possible to the inoperable equip-ment.
In the event the fire suppression water system becomes inoperable, immediate corrective measures must be taken since this system provides the major fire suppression capability of the plant. The raquirement for a twenty-four hour report to the Commission provides for prompt evaluation.of the acceptability of the corrective measures to provide adequate fire suppression capability for the continued protection of the nuclear plant.
CALVERT CLIFFS - UNIT 2 B 3/4 7-6 Amendment No. JJ, (3,4 6
O ADMINISTRATIVE CONTROLS 6.10 RECORD RETENTION
~
6.10.1 The following records shall be retained for at least five years:
a.
Records and logs of facility operation covering time interval at each power level.
b.
Records and logs of principal maintenance activities, inspections, repair ^and replacement of principal items of equipment related to nuclear safety.
c.
All REPORTABLE EVENTS.
d.
Records of surveillance activities, inspections and calibrations required by these Technical Specifications.
e.
Records of reactor tests and experiments.
f.
Records of changes made to Operating Procedures.
g.
Records of radioactive shipments.
h.
Records of sealed source and fission detector leak tests and results.
i.
Records of annual physical inventory of all sealed source material of record.
6.10.2 The following records shall be retained for the duration of the Facility Operating License:
a.
Records and drawing changes reflecting facility design modifi-cations made to systems and equipment described in the Final Safety Analysis Report.
b.
Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
c.
Records of facility radiation and contamination surveys.
CALVERT CLIFFS - UNIT 2 6-19 Amendment No.M 75
ADMINISTRATIVE CONTROLS d.
Records of radiation exposure for all individuals entering radiation control areas.
Records of gaseous and liquid radioactive material released to e.
the environs.
f.
Records of transient or operational cycles for those facility components identified in Table 5.7.1.
g.
Records of training and qualification for current members of the plant staff.
h.
Records of in-service inspections performed pursuant to these Technical Specifications.
1.
Records of Quality Assurance activities identified in the NRC approved QA Manual as lifetime records.
J.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
k.
Records of meetings of the POSRC and the OSSRC.
1.
Records of Environmental Qualification which are covered under the provisions of paragraph 6.13.
Records of the service lifes of all safety related snubbers l
m.
including the date at which the service life commences and associated installation and maintenance records.
Lil R,JIATION PROTECTION PROGRAfi Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR Part 20:
A high radiation area in which the, intensity of radiation is a.
greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a High Radiation Area and entrance thereto shall be controlled by issuance of a Special or Radiation Work Permit and any individual or group of individuals permitted to enter such areas shall be provided with a radiation monitoring device which continuously indicates the radiation dose rate in the area.
CALVERT CLIFFS - UNIT 2 6-20 Amendment No. //g,106