ML19347A479
| ML19347A479 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 04/03/1979 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19347A478 | List: |
| References | |
| NUDOCS 7904190364 | |
| Download: ML19347A479 (5) | |
Text
k p'
^<.
UNITED STATES
[,.
.4 NUCLEAR REGULATORY COMMisslON 5 '.f((
h WASHINGTON,0. C. 20555 YANKEE ATOMIC ELECTRIC COMPANY DOCKET NO. 50-29
~
YANKEE NUCLEAR POWER STATION (YANKEE-ROWE)
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 57
~
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 February 7,1979 (Supplement No. 3 to Proposed Change No.158), as supplemented by letter dated March 5,1979, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility yill operate in conformity with the tpplication, 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 de ense and security or to the health and safety of f
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.
79041903
+
l'
- :: :,1;~L, : -
, 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-3 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 57, 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
}.. ::,vc..z h )?f Y%*
Dennis L. Ziemann,vChief Operating Reactors Branch #2 Division of Operating React, ors
Attachment:
Changes to the Technical Specifications Date of Issuance: April 3,1979
...k ' *;
}p
=
- . =
.=
=
a=
.i... L.:.
_ a
6 ATTACHMENT TO LICENSE AMENDMENT NO. 57 FACILITY OPERATING LICENSE NO. DPR,3, u
CSCKET NO. 50-29 Revise Appendix A Technical Specifications by removing the page identified below and inserting the enclosed page. The revised page includes the captioned amendment number and cortrins a vertical line indicating the area of change.
Remove Insert 3/4 9-8 3/4 9-8
~
The overleaf page is also enclosed for document completeness.
=-
..;s P
i
-w l
'C*,'*.
'. :: L l
.. -.. ~........
.. - -. ~ -. - - - - -+-
- ' ~
' -i
^
l
- :< ::55 :. :'
.:2 r-
== =:=- = +:.^==:'-
=j
~ ~ = -
t j.
i
(.
! FIF;.'E' :*:s OPEF.: tic::s i
, I'~:IL3 TMv: S A'.' ITY
'"N:7'JLATOP. CRANE OPERABILITY
' LIM: TIN 3 CONDITION FOR OPERATION 3.9.6 Control rods and fuel assemblies shall be har.dled one-by-ene r'itn an OPERABLE snield tank cavity manipulator :rane ar.: universal nandling tooi with:
a.
A minimum capacity of 900 pounds, and l
b.
An c'verload cut off limit g,4800 pounds.
A:PLICABILITY:
During movement of control rods er fuel assemblies within the reactor pressure vessel.
ACTIO!!:
With the requirements for crane and handling tool OPERASILITY not satisfied, suspend use of the inoperable manipulator, crane or handlir.g tool from operations involving the movement of control rods and fuel assemblies within the reactor pressure vessel.
The provisiens of Sps:ification 3.0.3 are not appli' cable.
SURVEILLANCE REOUIREMENTS 4.9.6 The manipulator crane and handling tool used for movement of '
control rods or fuel assemblies within the reactor pressure vessel shall be demonstrated OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of such operations by performing a load test 'of a't least 900 pounds, demon-strating an automatic load cut off when the crane load ex:eeds 4800 pounds, and verifying proper opertation of the handling t:ol.
l P00R ORIGINAL '
A t : +-- *:. 27, 58 O
\\
(
j REFUELI.'iG OPERATIONS L_.
C1ANE T2AVEL - SPENT FUEL PIT
~'
LIMITIf;3 CONDITION FOR OPERATION E
1 t'
3. 9. 7 Loads in excess of Z3 pounds shall be pr:hibited from travel over the spent fuel pit except for the:
t r
}
a.
Spent fuel pit building roof hatches, I
b.
Spent fuil inspection stand, 1
c.
Fuel handling equipment i
1 l
d.
Spent fuel rack:.
e.
Temporary gate. and i
f,.
Shielding panels.
APPLICABILITY: With fuel assemblies in the spent fuel _ pit. _ _
- i 8
ACTION:
7 With the requirements of the above specification not satisfied, place the crane load in a safe condition. The provisions of Specification i
3.0.3 are not applicable.
t l
SURVEILLANCE REQUIREMENTS 1
p F
4.9.7 Loads in excess of 900 pounds shall be prevented from traveling h
over the spent fuel pit by administrative control except that the:
1
)
a.
Spent fuel pit building roof hatches, the spent fuel inspection stand, the fuel handling equipment, the spent fuel racks, the I
temporary gate support brackets, and tr.e shielded work platform may travel over the spent fuel pit in accordance with approved written l.'
precedures.
5;ent fuel s:Orage ra:ks, the spent fuel ins:e::i:n s and, :ne e :crary gate su::or: brackets, ane :ne sr's :s: w:N :latf:m s 111 be :reven e: fr:- traveling ever fuel assi :l'es in tre spent l
l
- .ai pit by acr.in'strative control, anc
.si hanciing e:uieren; when revec for rain;e-a :e senil be :re-5-ed fr:
traceling ever fuel asser.biies '- : i s:er.: fuel pit by 1:-inistra:ive : -trol, k _. __... _ _
_ __. ~ i" O i~ ef_: _*.:. 3 3 '_. b.). 5
-