ML19339A428
| ML19339A428 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 07/22/1976 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19339A427 | List: |
| References | |
| NUDOCS 8011030786 | |
| Download: ML19339A428 (7) | |
Text
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UNITED STATES f.,
1 NUCLEAR REGULATORY COMMISSION
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WASHINGTON. D, c. 20566 s,,
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YANKEE ATOMIC ELECTRIC COMPANY DOCKET NO. 50-29 YANKEE NUCLEAR POWER STATION (YANKEE-RONE)
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 29
, License No. DPR-3 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Yankee Atomic Electric Company (the licensee) dated August 18, 1975 and supplement dated January 29, 1976, complies with the standards and requirements of the Atomic Energy 8.et of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Part 50, 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.
After weighing the environmental aspects involved, the issuance of this amendment is-in 'accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satis fied.
2.
Accordingly, the license is amended by a change to the Technical Specifications as indicated in the attachment to this license amendcent.
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80110307 W
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- 3. - This license amendment is effective as of the date of its issuance..
FOR TiiE, NUCLEAR REGULATORY COR!ISSIO.4 s.
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7, A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the
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Technical Specifications Date of Issuance: July.22, 1976 e
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ATTACHMENT TO LICENSE AFEND5ENT NO. 29 FACILITY OPERATING LICENSE NO. DPR
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DOCKET NO. 50-29 Revise Appendix A as follows:
Remove page 19 and insert revised page 19 Add pages 19a and 19b and Table F.2-1 I
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O LD1ITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS F.1 ROD DROP TI?iE j
LIMITING CC::DITIO:: FOR OPER.\\ TION 1
The individual control rod dron times shall be < 2.50 seconds j
from loss of stationary gripper coil voltage to 6 inch coil j
entry with:
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avg 1 511 and; a.
b.
all reactor coolant pumps operating.
APPLICABILITY: llot Standby, ACTION:
i a.
With the drop time of any rod determined to exceed the above limit, restore the drop time to within the above limit prior to proceeding to startup or power operation.
b.
With the rod drop times within limits but determined with 3 reactor coolant pumps operating, operatien may proceed provided tnermal power is restricted to < 75 perecct ot rated thermal power.
SURVEILLANCE REQUIRD1ENTS The rod drop time of control rods shall be demonstrated through measurement prior to reactor criticality:
a.
for all rods following each removal of the reactor vessel head; b.
for specifically affected individual rods following any maintenance on or modification to the rod drive system which could affect the drop time of those specific rods, and; c.
at 1 cast once per 18 months.
Amendment No. 29
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-19a-l'. 2 SilOG SUIPl&SSORS (SNUBBERS)
LIMITING (:0NDITIONS During all modes of operation except Cold Shutdown and Refueling, all snubbers listed in Table F.2-1 shall be operable except as described below, a.
Reactor operation is only permitted for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after the time a snubber is determined to be inoperable unless the snubber is sooner made operable or replaced.
b.
If the requirements of "a" 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 />.
Snubbers may be added to safety related systems without prior c.
License Amendment to Table F.2-1 provided that a revision to Table F.2-1 is included with a subsequent License Amendment reque s t,
d.
If a snubber is determined to be inoperable while the reactor is in a cold shutdown or refueling mode, the snubber shall be made operabic or replaced prior to exceeding the cold shutdown mode.
APP' I CABI LITY :
All modes of operation except for Cold Shutdown and Re fue ling.
SUR'EILLA';CE REQUIREbENTS The following surveillance requirements shall apply to all hydraulic sntibers listed in Table F.2-1.
a.
All hydraulic snubbers whose seal materials has been demonstrated by operating experience, lab testing or. analysis to be compatible with the operating environment shall be vistially inspected in accordance with the following schedule:
Nunber of snubbers found Next required inoperable during inspection inspection interval or inspection interval 0
IS months + 255 1
12 months 7 25'.
2 6 months 7 255 3, 4 124 days 7 25',
5,6,7 62 days
+ 25'4
>8 31 days
+ 25's The required inspection interval shall not be lengthened more than one step at a time.
The initial inspection shall be performed within six months from the date of issuance of these specifications.
It shall be assumed that the facility has been on a six months, + 25', inspec-tion interval.
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b.
All hydraulic snubbers whose seal materials are other than ethylene propylene or other material that has been demonstrated to be compatible with the operoting environment shall be
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visually inspected for operability every 31 d,ays.
The visual inspection to verify snubber. operability shall c.
include, but not necessarily limited to:
inspection of the hydraulic fluid reservoir, fluid connections, and linkage connections to the piping and anchor.
d.
Once each refueling cycle, a representative sample of approxi-mately 10% of the hydraulic snubbers shall be functionally tested for operability including verification of proper piston movement, lock-up and bleed.
For each unit and subsequent unit tested that proves inoperable, an additional appro'ximately 10% of the snubbers
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shall be functionally tested until no more failures are found or all snubbers have been tested. Snubbers of rated capacity greater than 50,000 lbs. need not be functionally tested.
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Amendment No. 29 t__
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Table F.2-1 1
SAFETY RELATED SHOCK SUPPRESSORS (SNUBBERS)
Accessible Ouring Snubber No.
Protected-System-Location' Normal Opera; ion liSS 19A
!!SS 19B Pressurizer Relief Valve Pressurizer Cubicle Yes llSS 20A IfSS 208 ilSS 21 IISS 22 Pressurizer Relief Valve Pressuri:cr Cubicic Yes
!!SS 23 Discharge Line IISS 24 J
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1 Amendment No. 29 i
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