ML20080B900
| ML20080B900 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 08/01/1983 |
| From: | Lainas G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20080B904 | List: |
| References | |
| NUDOCS 8308180545 | |
| Download: ML20080B900 (10) | |
Text
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UMITED STATES
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NUCLEAR REGULATORY COMMISSION
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' J WASHINGTON, D. C. 20555 t,
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BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT N0. 1 AMENDMENT TO FACILITY OPERATING' LICENSE Amendment No. 86 License 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 March 7, 1983, as supplemented May 24, 1983, 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 amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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8308180545 830801 PDR ADOCK 05000317 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-53 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices t
A and B, as revised through Amendment No. 86, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION k
Gus C. Lainas, Assistant Director for Operating Reactors Division of Licensing
Attachment:
Changes to the Technical Specifications
'Date of Issuance: August 1,1983 e
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ATTACHMENT TO LICENSE AMENDMENT NO.
M ILITY OPERATING LICENSE NO. DPR-53 DOCKET NO. 50-317
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Replace the following pages of the Appendix A Technical Specif.ications with the enclosed pages as indicated. The revised pages tire identified by Amend-ment number and contain vertical lines indicating the aren of change. The corresponding overleaf pages are'.also providea to maintain documentjompleteness.
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'S Pages 3/46-8 3/4 6-9 3/4 6-9a (new figure) 3/4 6-9b (new figure)'
3/4 6-9c (new figure) 3/4 6-9d (renumbered)
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CONTAINMENT SYSTEMS AIR TEMPERATURE LIMITING CONDITION FOR OPERATION 3.6.1.5 Primary containment average air temperature shall not exceed 120*F.
APPLICABil.ITY: MODES 1, 2, 3 and'4.
ACT10N:- f With the containment average air temperature > 120*F, reduce the average air,temperatu're to within the limit within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or be in at least HOT STANDBY within'the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
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u SUR E LLANCE REQUIREMENTS 4.6.1.5 The piimary containment average air temperature shall be the.
arithmetical average of the temperatures at the_following locations and shall be determined at least once per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:
Lccation' a.
Containment Dome b.
Containment Reactor Cavity g
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CA VERT CLIFFS - UNIT 1 3/4 6-7 l
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CONTAINMENT SYSTEMS CONTAINMENT STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.6 The structural integrity of the containment shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.6.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
a.
With the containm nt structure exhibiting evidence of possible abnormal degradation per Specification 4.6.1.6.1, perform an engineering evaluation demonstrating the ability of the containment structure to continue to perform its design function.
If continued contaimnent integrity cannot be assured by engineering evaluation within 90 days of the surveillance test, be in COLD SHUTDOWN within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
The requirements of Specifica-tion 3.0.4 are not applicable.
b.
With the structural integrity of the containment not conforming at a level consistent with the acceptance criteria of Specification 4.6.1.6.2 or 4.6.1.6.3, restore structural integrity or complete an engineering evalua-tion that assures structural integrity prior to increasing Reactor Coolant System Temperature above 200?F.
SURVEILLANCE REQUIREMENTS i
4.6.1.6.1 Containment Tendons.
The containment tendons' structural integrity shall be denonstrated at five year intervals. The tendons' structural integrity shall be demonstrated by:
a.
Detennining that for a representative sample of at least 9 tendons (3 dome, 3 vertical, and 3 hoop), each tendon has a normalized lift-off force equalling or exceeding its lower limit expected range for the time of the test (see Figures 4.6-1,
-2, and -3).
If the normalized lift-off force of any one tendon in a group lies between the lower limit expected range and the lower bound individual, an adjacent tendon on each side shall be checked for lift-off force.
If both of these tendons are found acceptable, the surveillance program may proceed considering the single deficiency as unique and acceptable.
If either of the adjacent, tendons is found unacceptable, it shall be considered as evidence of possible abnormal degradation of the containment structure.
In addition, more than one unacceptable tendon out of those selected for surveillance (from all three tendon groups) shall be considered as evidence of possible abnormal degrada-~
tion of the contaimnent structure.
If the normalized lift-off force of any single tendon lies below the lower bound individual, the occurrence should be considered as evidence of possible abnormal degradation of the containment structure.
CALVERT CLIFFS - UNIT 1 3/4 6-8 Amendment No. 86
l CONTAINMENT SYSTEMS j
I SURVEILLANCE REQUIREMENTS (Continued) l In addition, determining that the average of the normalized lift-off forces for each sample population (hoop, vertical, dome) is equal to or greater than the required average prestress level; 536 kips for hoop tendons, 622 kips for vertical tendons, and 555 kips for dome tendons (reference Figures 4.6-1,
-2, and -3).
If the average is below the required average prestress force, it shall be considered as evidence of possible abnormal degradation of the containment structure.
b.
Removing one wire from each of a dome, vertical and hoop tendon checked for lift off force, and determining over the entire length of the wire:
1 1..
The extent of corrosion, cracks, or other damage. The presence of abnormal corrosion, cracks or other damage shall be considered evidence of possible abnormal degradation of the containment structure.
2.
A minimum tensile strength value of 240 Ksi (guaranteed ultimate strength of the tendon material) for at least three wire samples (one from each end and one at mid-length) cut from each removed wire.
Failure of any one of the wire samples to meet.the minimum tensile strength test is evidence of possible abnormal degrada-l tion of the containment structure.
I c.
Perform a chemical analysis to detect changes in the chemical properties of the sheath filler grease.
Any unusual changes in physical appearance or chemical properties that could adversely affect the ability of the filler grease to adhere to the tendon wires or otherwise inhibit corro-sion shall be reported to the Commission pursuant to Specification 6.9.1.
4.6.1.6.2 End Anchorages and Adjacent Concrete Surfaces. The structural integrity of the end anchorages and adjacent concrete surfaces shall be demonstrated by j >ietermining through inspection that no apparent changes have occurred in the visual appearance of the end anchorage concrete exterior surfaces or the concrete crack patterns adjacent to the end anchorages.
Inspections of the concrete shall be performed during the Type A containment leakage rate tests (reference Specification 4.6.1.2) while the containment is at its maximum test pressure.
4.6.1.6.3 Liner Plate. The structural integrity of the containment liner plate shall be determined during the shutdown for each Type A containment leakage rate test (reference Specification 4.6.1.2) by a visual inspection of the plate and verifying no apparent changes in appearance or other abnormal degradation.
4.6.1.6.4 Report:. Any abnormal degradation of the containment structure detected during the above required tests and inspections shall be reported to the Commission pursuant to Specification 6.9.1.
This report shall include a description of the tendon condition, the condition of the concrete (especially at tendon anchorages),
the inspection procedures, the tolerances on cracking, and the corrective actions taken.
CALVERT CLIFFS - UNIT 1 3/4 6-9 Amendment No. 86
i 800 a
700 Expected 671 Lower Limit g
Expected Range o
635 636 g
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b 600
% 600 Required Average 536 536 517
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500 individual N
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10 40 100 Years Figure 4.6-1 Normalized Prestress Hoop Tendons CALVERT CLIFFS - U::IT 1 3/4 6-9a Amendment No. 86
800 t
700 Expected 680
- Lower Limit g
Expected Range t
643 5
645 H
g Requ. ired Averag%
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622 622 c.
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% 608 600 595 Lower Bound Individual
% 560 500 -
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1 10 40 100 Years Figure 4.6-2 Normalized Prestress Vertical Tendons CALVERT CLIFFS
'JNIT 1 3/4 6-9b Amendment No. 86 1
800
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700 Expected 654 8
E Lower Limit Expected Range P,
618 I
'N 613
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% 577 Required Average 555 54D %
Lower Bound Indiv. idual
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m 500
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10 40 100 Years Figure 4.6 3 Normalized Prestress Dome Tendons CALVERT CLIFFS - UNIT 1 3/4 6-9c Amendment No. 86
CONTAINMENT SYSTEMS CONTAINMENT PURGE SYSTEM LIMITING CONDITION FOR OPERATION I
3.6.1.7 The containment purge supply and exhaust isolation valves shall be closed by isolating air to the air operator and maintaining the solenoid air supply valve deenergized.
APPLICABILITY:
MODES 1, 2, 3 and 4 ACTION:
With one containment purge supply and/or one exhaust isolation valve open, a.
close the open valve (s) within one hdur or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With one containment purge supply valve inoperable due to high leakage, repair the valve (s) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
1 SURVEILLANCE REQUIREt1ENTS i
4.6.1.7 The 48-inch containment purge supply and exhaust isolation valves shall be determined closed at least once per 31 days, by verifyi'ng that power to the solenoid valve is removed.
l CALVERT CLIFFS - UNIT 1 3/4 6-9d Amendment No.f f, 86
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