ML19343A554
| ML19343A554 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 01/29/1976 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19343A552 | List: |
| References | |
| NUDOCS 8011140628 | |
| Download: ML19343A554 (5) | |
Text
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ATTACID!EhT A y
c, x,c y Regulatory Docket Eila F.2 M DRAULIC SNUBBERS LIMITING CONDITIONS During all nodes of operation except Cold Shutdown, all hydraulic snubbers listed in Table F.2-1 shall be operable except as described below, 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 n.
time a hydraulic snubber is determined to be inoperable unless the snubber is repaired 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 />.
c.
Snubbers may be added to safety related systems in accordance with 10 CFR 50.59 and a revised Table F.2-1 shall be inc;aded with a subsequent License Amendment.
d.
If a hydraulic snubber is determined to be inoperabic while the reactor is in a Cold Shutdown mode, the snubber shall be made operabic prior to reactor startup, i
APPLICABILITY:
All modes of operation except for Cold Shutdown.
SilRVFTil.ANCF RFOllTHFMFNTF, The following surveillance requirements shall apply to all hydraulic snubbers 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 co:apatibic with the operating environment shall be visually inspected in accordance with the following schedule:
Number of snubbers found Next required inoperabic during inspection inspection interval or inspection interval 0
18 months + 25'e 1
12 months 7 25'e 2
6 months 7 25's 3, 4 124 days T 25'e 62 days
+ 25*6 5,6,7
>8 31 days
_ 2 5 '.
+
The required inspection interval shall not be lengthened more than one step at a time.
'he 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 operating environment shall be visually inspected for operability every 31 days.
i The visual inspection to verify snubber operability shall c.
include, but not necessarily limited to:
irispection' of the 4
hydraulic fluid reservoir, fluid connections, and linkage connections to the piping and supports.
d.
Once each refueling cycle, a representative sample of approxi-mately 10% of the snubbers.shall be functionally tested for j
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operability including verification of proper piston move.nent, lock-up and biced. For each' snubber tested that proves inoper-able, an additional approximately 10% of the snubbers shall be functionally tested until no more failures are found or all snubbers have been tested.
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Table F.1-1 e
SAFEN RELATED flYDRAULIC SNUBBERS Accessible During Snubber No.
Protected System Location Normal Operation llSS 19A I 3I Pressurizer Relief Valve Pressurizer Cubicle Yes l S 20 llSS 20B llSS 21 IISS 22 Pressurizer Relief Valve Pressuri:cr Cubicle Yes llSS 23 Discharge Line llSS 24 O
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_e-ATTACIIMENT B F.
LIMITING CONDITIONS FOR OPERATION AND SURVEILIANCE REQUIRE'4ENTS F.1 ROD DROP TIME d -s I f ' '
LIMITING CONDITION FOR OPERATION The individual control rod drop times shall be < 2.50 scconds from loss of stationary grippet coil voltage to 6 inch coil cntry with:
T 0
avg 3.511 and; a.
b.
all reactor coolant pumps operating.
APPLICABILITY: Ilot Standby.
ACTION:
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, operation may proceed proviaca tneraal power is restricted to < 75 percent or rated thermal power.
SURVEILIANCE REQUIREMENTS 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 least once per 18 months.
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NRC DISYLftutedtn 80!@ FKM PART 50 DOCIUFV t'.YNI AL' (I EMPORARY FORM)
CONTROL f40: 1054 c
7 FILE:
Uto:.*,: Yankee Atomic Elec. Co.
DATE OF DOC DATE REC'D LTR TWX RPT OTHER Westborough; Mass. 01581 1-29-76 2-4-76 XX L K..Vandenburnh TO:
ORIG CC OTHER SEiiT H:10 PDR XX NRC 3 signed 37 SENT LOCAL PDR XX CiASS UNC L ASS PROPINFO INPUT NO CYS RFC'D DOCKET NO:
XXX 40 50-29 DESCRIPTION: Ltr notarized 1-29-76 requests af::f NCLOSU R ES:
ATTACHMENT'S A & B, consists for amdt to OL/DPR-3/ Tech Spec change of props ed changes to Tech Specs in re to hydrauli.c snubbers...
relative to hydraulic snubbers & trans the following: (PROPOSED CHANGE NO. 128, SUFFL #1)
(40 cys enci rec'd)
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