ML19274E410
| ML19274E410 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 03/02/1979 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19274E407 | List: |
| References | |
| NUDOCS 7903260036 | |
| Download: ML19274E410 (10) | |
Text
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UNITED STATES
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[*2 NUCLEAR REGULATORY COMMISSION
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.....f C0t!!1ECTICUT YAt!KEE AT0filC POWER C0f pat!Y DOCKET t!0. 50-213 HADDAtt PJECK PLAtlT AMENDMENT TO FACILITY OPERATING LICEt!SE Amendment No. 31 License No. DPR-61 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Connecticut Yankee Atomic Power Company (the licensee) dated February 27,1979; as supplemented by letter dated March 2,1979, complies with the standards and requirements of the Atomic Energy Act of 195A, as ! mended (the Act), and the Commission's rules and regulaticns sc. 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 authori:ed 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 recuirements have been satisfied.
79032600%
.- 2.
- ccordingly, the license is amended by changes to tPs Technical Specifications as indicated in the attachment : this license amendment and paragraph 2.C.(2) of Facility Operatin; License fio. DPR-61 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appencices A and B, as revised through Amendment rio. 31, 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 f1UCLEAR REGULATORY CC'tMISSI0t1
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Dennis L. Ziemann,{hief Operating Reactors Branch =2 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: March 2,1979
ATTACHMENT TO LICENSE Af tENDf1ENT fl0 31 FACILITY OPERATIflG LICENSE N0. OPR-61 DOCKET fl0. 50-213 Revise the Appendix A Technical Specifications by deleting the following pages and inserting the enclosed pages. The revised pages contain the captioned amendment number and vertical lines reflecting the area of change.
Removes Pages Insert Pages 3-38 3-38 3-38a 3-38a 3-38b Table 3.19-1 Table 3.19-1 4-26 4-26 4-27 4-27 4-28 4-28 4-29 4-29
3.19 Hydraulic Snubbers Applicability:
This specification applies to hydraulic snubbers which are attached to the reactor coolant system and all other safety related systems whose structural integrity is needed to be maintained during and follo. wing a seismic or other event initiating dynamic loads.
Objective:
To re reactor coolant system and other safety related system motions are adequately restricted should a design basis earthquake or other transient occur.
Specification:
A.
During all modes of operation except Cold Shutdown and Refuel, all hydraulic snubbers listed in Table 3.19-1 shall be operable except as noted in 3.19.B through 3.19.D below.
B.
From and after the time that a hydraulic snubber is determined to be inoperable, continued reactor operation is permissible only during the succeeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> unless the snubber is sooner made operable or replaced.
C.
If the requirements of A and B cannot be met, an orderly shutdown shall be initiated and the reactor shall be in a cold shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
D.
If a hydraulic snubber is determined to be inoperable while the reactor is in the shutdown or refuel mode, the snubber shall be made operable or replaced prior to reactor startup.
E.
Snubbers may be added to safety related systems without prior license amendment to Table 3.19-1 provided that a revision to Table 3.19-1 is included with the next license amendment request.
Bases Snubbers are designed to prevent unrestrained component motion under dynamic l loads as might occur during an earthquake or severe transient. while allow-ing normal thermal motion during startup and shutdown.
The consequence of an inoperable snubber is an increase in the probability of structural damage to components as a result of a seismic or other event initiating dynamic l
loads.
It is therefore required that all hydraulic snubbers required to protect the primary coolant system or any other safety system or component be operable during reactor operation.
3-38 Amendment" No. 9, 31
Bases Continued Because the snubber protection is required only during relatively low probability events, a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is allowed for repairs c replacements.
In case a shutdown is required, the allowance of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> to reach a cold shutdown condition vill permit an orderly shutdown consistent with standard operating procedures. Since plant startup should not commence with knowingly defective safety related equipment, Specification 3.19 prohibits startup with inoperable snubbers.
3-38a Amendment tio. $,31
TABLE 3.19-1 SAFETY RELATED llYDRAULIC SNUBBERS SNUBBER NO.
LOCATION SNUBBER IN 111C11 SNUBBFRS
- SNUBBERS RADIATION AREA ESPECIALLY INACCESSIBLE ACCESSIBLE DURING SiluTDOWN*
DIFFIC JLT TO DURING NORMAL DURING NORMAL REMOVE OPERATION OPERATION 1*
- Neutron Shield X
X X
Tank-RX Vessel 2*
- X X
X J*
- X X
X 4*
- X X
X ACCESSIBLE:
Snubbers which can be visually inspected remotely as per specification 4.13 during normal power operation.
INACCESSIBLE:
Snubbers which cannot be visually inspected during normal power operation. This is snubbers numbers 1 to 4.
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- Modifications to this Table due to changes in high radiation areas should be submitted to the NRC as 5
part of the next license amendment.
=
P
- These hydraulic snubbers have a rated capacity of greater than 50,000 lbs.
l
4.13 Hydraulic Snubbers Applicability This Specification applies to the hydraulic snubbers listed in Table 3.19-1 and required to be OPERABLE in accordance with Specification 3.19.
Objective To provide assurance of hydraulic snubber operability over the plant service lifetime.
Specification A.
All hydraulic snubbers whose seal material has been demonstrated by operating experience, lab testing or analysis to be compatible with the operating environment shall be visually inspected to verify their operability in accordance with the following schedule:
Snubbers are categorized in two groups " Accessible or Inaccessible" based on their accessibility for inspection during reactor operation".
Schedule Al - Accessible Number of Snubbers Found Inoperable During Inspection Next Required Or During Inspection Interval Inspection Interval 0
18 months + 25%
1 12 months + 25%
2 6 months f; 25%
3, 4 124 days + 25%
5,6,7 62 days f;25%
>8 31 days + 25%
The required inspection interval shall not be lengthened more than one step at a time.
4-26 Amendment No. 9, 31
Schedule A-II - Inaccessible Snubber shall be inspected during each reactor refueling.
B.
All hydraulic snubbers whose seal materials are other than ethylene phropylene or other material that has been demonstrated to be compatible with the operating environment shall be visually inspected for operability in accordance with the following schedule:
Schedule B-I - Accessible Each snubber accessible shall be visually inspected for operability every 31 days + 25%.
Schedule B-II - Inaccessible Each snubber shall be visually inspected for operability each reactor refueling and cold shutdown.
C.
The visual inspection shall include verification of proper orientation, proper snubber attachment and indications of excessive fluid leakages, D.
1.
Once each refueling cycle a representative sample of the installed snubbers shall be functionally tested for operability including verification of proper piston movement, and bleed rate. The representative snubber shall be at a minimum one snubber per system.
2.
For each unit and subsequent unit found inoperable, an additional snubber shall be so tested until no additional failures are found or all units have been t2sted.
3.
Snubbers of rated capacity greater than 50,000 lbs. need not be functionally tested.
4-27 Amendment No. $, 31
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Bases All safety related hydrualic snubbers are visually inspected for overall integrity and operability. The inspection will include verification of proper orientation, adequate hydrualic fluid level and proper attachment of snubber to piping and structures.
The inspection frequency is based upon maintaining a constant level of snubber protection. Thus the required inspection interval varies inversely with the observed snubber failures. The number of inoperable nubbers found during a required inspection determines the time interval for the next required 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 previous schedule.
Experience at operating facilities has shown that the required surveillance program should assure an acceptable level of snubber performance provided that the seal materials are compatible with the operating environment.
Snubbers containing seal material which has not been demonstrated by operating experience, lab tests or analysis to be compatible with the operating environment should be inspected more frequently (every month) until material compatability is confirmed or an appropriate changeout is completed.
Examination of defective snubbers at reactor facilities and material tests performed at several laboratories (Reference 1) has shown that millable gum polyurethane deteriorates rapidly under the temperature and moisture conditions present in many snubber locations. Al though molded polyurethane exhibits greater resistance to these conditions, it also may be unsuitable for application in the higher temperature environments. Data are not currently available to precisely define an upper temperature limit for the molded polyurethane. Lab tests and in-plant experience indicate that seal materials are available, primarily ethylene propylene compounds, which should give satisfactor performance under the most severe conditions expected in reactor installations.
Amendment No. 31
To further increase the assurance of snubber reliability, functional tests should be performed once each refueling cycle. These tests will include stroking of the snubbers to verify proper piston movement, a
lock-up and bleed. One of each of the snubbers per system represents I
an adequate number for such tests. Observed failures on these samples will require testing of additional units. Snubbers of rated capacity greater than 50,000 lbs. are exempt from the functional testing requirements because of the impracticability of testing such large units.
Mechanical snubbers are inspected by the Inservice Inspection Program for their structural integrity.
l (1 ) Report-H. R. Erickson, Bergen Patterson to K.R. Goller, NRC, October 7,1974
Subject:
Hydraulic Shock Sway Arrestors 4-29 Amendment No. 31
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