ML15218A093
| ML15218A093 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 07/10/1979 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML15218A094 | List: |
| References | |
| NUDOCS 7908080116 | |
| Download: ML15218A093 (11) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 74 License No. DPR-38
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by the Duke Power Company (the licensee) dated August 22, 1978, as supplemented April 30, 1979, 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.
7908080 /(6
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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 3.B of Facility Operating License No.
DPR-38 is hereby amended to read as follows:
3.B Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 74 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 ert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 10, 1979
UNITED STATES 0*NUCLEAR REGULTORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 74 License No. DPR-47
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by the Duke Power Company (the licensee) dated August 22, 1978, as suppl emented April 30, 1979, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commnission's rules and regulations set forth in 10 CFR Chapter 1; 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 (1) that the activities authorized I
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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- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.3 of Facility Operating License No.
DPR-47 is hereby amended to read as follows:
3.8 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 74 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 bert.W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifi cations Date of Issuance:
July 10, 1979
UNITED STATES NUCLEAR REGULATORY COMMIION WASHINGTON, 0. C. 20555 DUKE POWER COMPANY DOCKET NO. 50,287 OCONEE NUCLEAR STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 71 License No. DPR-55
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by the Duke Power Company (the licensee) dated August 22, 1978, as supplemented April 30, 1979, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissionl's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in confomity with the application, the provisions of the Act, and the rules and regulations of the 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 Commission's regulations and all applicable requirements have been satisfied.
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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 3.B of Facility Operating License No.
DPR-55 is hereby amended to read as follows:
3.B Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 71 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 Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 10, 1979
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 74 TO DPR-38 AMENDMENT NO. 74 TO DPR-47 AMENDMENT NO. 71 TO DPR-55 DOCKETS NOS. 50-269, 50-270 AND 50-287 Revise Appendix A as follows:
Remove Pages Insert Pages 4.18-1 4.18-1 & 4-18-2 4.18-la 4.18-2 4.18-6 4.18-6 4.18-11 & 4.18-11a 4.18-11 Changes on the revised pages are indicated by marginal lines.
4.18 HYDRAULIC SHOCK SUPPRESSORS (SNUBBERS)
Aptlicability Applies to hydraulic shock suppressors used to protect the Reactor Coolant System or other safety-related systems.
Objective To verify that required hydraulic shock suppressors are operable.
Specification 4.18.1 All hydraulic snubbers listed in Table 4.18-1 whose seal material has been demonstrated by operating experience, lab testing or analysis to be compatible with the operating environment shall be visually in spected.
This inspection shall include as a minimum hydraulic fluid reservoir, fluid connections, and linkage connections to the piping and anchor to verify suppressor operability in accordance with the following schedule:
Number of Suppressors Found Next Required Inoverable During Last Insnection Inspection interval 0
18 months Z 5%
1 12 months +/- 25%
2 6 months +/- 25%
3,4 4 months +/- 254 5,6,7 2 months +/- 25%
>8 1 month
+/- 25' Note:
(1)
The required inspection interval shall not be lengthened more than one step per inspection.
(2)
Suppressors may be categorized in two groups, "accessible" or "inaccessible", based on their accessibility during reactor operation. These two groups may be inszected independently according to the above schedule.
4.18.2 All hydraulic snubbers with seal material not fabricated from ethy lene propylene or other materials-demonstrated compatible with the operating environment shall be visually inspected for operability once every month.
4.18.3 A representative sample of 10 hydraulic shock suppressors or approxi mately 10 percent of the hydraulic suppressors installed, whichever is less, shall be functionally tested for operability each refueling outage.
This test shall include verification of proper piston movement, lockup and bleed. For each suppressor determined to be inoperable, an addi tional 10 percent or 10 suppressors, whichever is less, shall be tested until no more failures are found or all suppressors have been tested.
Suppressors with a rated capacity greater than 30,000 lbs. are exempted from this requirement.
Amendments Nos. 74, 74,
& 71
- 41. 1
Bases All safety-related hydraulic suppressors are visually inspected for overall inte grity and operability. The inspection will include verification of proper orien tation, adequate hydraulic fluid level and proper attachment of suppressor to piping structures.
The inspection frequency is based upon maintaining a constant level of suppressor protection. Thus, the required inspection interval varies inversely with the observed inoperable suppressors.
The number of inoperable suppressors 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 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 pro gram 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 compatabilit7 is confirmed or an appropriate changeout is completed.
Examination of defective snubbiri at reactor facilities and material tests per formed at several laboratories I has shown that illable gum polyurethane deteriorates rapidly under the temperature and moisture conditions present in many snubber locations.
Although 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 propy lene compounds, which should give satisfactory performance under the most severe conditions expected in reactor installations.
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, lock-up and bleed. Ten percent or ten snubbers, whichever is. less, represents an adequate sample for such tests.
Observed failures on these samples should require testing of additional units.
Those snubbers designated in Table 4.18-1 as being in high radiation areas or esPeciall7 difficult to remove need not be selected for functional tests provided overability was previously verified. Snubbers of rated capacit7 greater than 50,000 lbs. are exempt from the functional testing requirements because of the impracticability of testing such large units.
REEREN C! S (1)Report H. R. Erickson, Bergen Paterson to K. R. Goller, NRC, October 7, 1974
Subject:
Hydraulic Shock Sway Arrestors Amendments Nos. 74, 74, & 71 4.18-2
TABILE 4.18-1 liaiiL 2 Safety Rlated Shock Stippressors (Snubbers)
JSuppress~ors Sup pressaors Suppressor ini ligli Especially Inaccessible During Radiation Area z kecqlaxr No.
SytiiDifficult Normal Operation During Shutdown-*
(I)
To R~emiove S2-124 Main Steama Linae (O1A)
X
.~2-125(A&B)X S2-127 S2-128 S2-129 2 -130 x
2 - 132 (A,,It,C D) 2-134 2-135 2-147 2 -149(A&II) x 2-151 2-152 11 2AX If RA x
11 2B1 X
1811 X
2-94 1 Main Steam Bypass to Condenser 2-944 (OIA-1) 2-945 2-3135 Hain fiteatu Supply to Auxiliary EquipwnenL (OIA-3) 2-1309 Hain Steiam Stipply to Emergency 2-1322 Fedwater Pimy Tuirbine (01A-4) 2-1323 2-1324 2-1 326 2-1327 2-1:129 2-1333
(D Uni 3 Siafty Reclated Shock Stipprefiiors (Sniubbers~)
0 upesr Suppiressors Suppressor In Iigi, T
Esecially JIaccessible Dluring Radiation Area
___h/~lie No.
SY Lemi I if icul L No rmial Overation Durin&_Shut dowijk To Rtemove If 7A Hain Feedwater Line (03)
X 111 40 If1411 x
3-1274 Emergency Feedwater Linae (63A) 3-1319 3-1280 3-5 606 3-5624 3-5628
~
1 IIOTSG Recirculation Systeum (04) 11 46 x
110 soX 11 52 X
If I Reactor Coolaut Systemx (50)
X 11 3 if14 x
II x
117 X
118 x
If19 x
If1 x
If111 x
11 12 x
If IA x
11 2A X
If 3A x
11 3A