ML19210E566
| ML19210E566 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png (DPR-28-A-055, DPR-28-A-55) |
| Issue date: | 10/26/1979 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19210E567 | List: |
| References | |
| NUDOCS 7912050292 | |
| Download: ML19210E566 (7) | |
Text
.
pn sec og#o, UNITED STATES
'i NUCLEAR REGULATORY COMMISSION
- c W ASHINGTON. D. C. 20555
%, v...../
VERMONT YANKEE NUCLEAR POWER CORPORATION DOCKET NO. 50-271 VERMONT YANKEE NUC.'. EAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 55 License No. OPR-28 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The acclication for amendment by Vemont Yankee Nuclear Power Corporation (the licensee) dated August 21, 1979, as supplemented October 5,1979 and October 5,1979, complies with the standards and requirenents 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 Comission; 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 Comission'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 Comission's regulations and all applicable require-ments have been satisfied.
1500 165 7912050 h
. 2.
Accordingly, the license is anended 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-28 is hereby amended to read as follows:
B.
Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through knendment No. 55, 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 af the date of its issuance.
FOR THE NUCLEAk REGULATORY C0ftMISSION
~.
Y.-r A - D,4'.
Thoma 4/ Ippolito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: October 26, 1979 1500 166
ATTACHMENT TO LICENSE AMENDMENT NO. 55 FACILITY OPERATING LICENSE NO. DPR-28 DOCKET NO. 50-271 Revise Appendix A as follows:
Remove the pages listed and replace with revised pages.
135 136 180-n5 180-01 1500 167
TABI.E 4.7.2.a PitillARY CONTAllillt'llT IS01.ATIOli VAI.VES VAI.VIS Slinlart 10 TYPC C l.I'AKAGE TI:STS Ilumiser of 1*cuer lla x ianusa Actton on Iaol at li.o Opciated V.ilves OpcratIng flammal In t t lat ins;
- e n..p (ll.. e l}
Valve lesent i f Icat inn l utin.a i.l Out boa rd Time (se i P.r.1 t loan Sarnal i
II.a l u *.I case I.lue luolation (2-110A, u & 2-86A,18) 4 4
5( ute 2)'
open CC l
llalu Se c.ne I.ine lis alo (2-74, 2-77) 1 1
35 a:losed SC i
lecc li culat ion I.oop S.is.pl e I.Inc (2-39, 2-40) 1 1
5 Closed SC 1
kiist til:.i l.an ge t o it. Juai.t e (10-$7, 10-66) 2 25 Closed SC 2
lis yuuli l'iour lia. ales (20-182, 20-83) 2 2si open CC 2
lu yuell l'.piipment lin.i lia (20-94, 20-95) 2 20 Opesa CC 1
payuct; Air Purge inlet (%-19-9) 1 10 Closed SC i
esayucil Air Puene inlet (18.- 19-11)
I to open CC i
De yuc t I l'os ri' L Vent Hullet ( II*- 19-7 A)
L 10 Clourd SC l
lin yu.. l l l'urr.e & Vent out let Ilypass (16-19-6A)
I 10 1:l uue.1 SC l
ps yuell & Siepprer.n ton Ili.au. lies-II.nin Enlaaust (16-19-7)
I 10 Closed SC i
Supps ession Cliau.luta Pui ge Supply (lfe-l'.a-10) 1 to Closed SC 1
Supps i :.r. loin 4:lian. lier Put ne & Veint Outlet C.6-19-7D) 1 10 Closed SC 1
- uppia
- :.: luu Cleaml.er Purge & Vent Outlet llypass (16-19-6B) 1 10 Opes; CC 1
1.nh.in.e so St.iu.II.y C.is Ti cat ment System (th-19-6) 1 10 Open CC
~l s '..u s il um. u t P>isce Supply (If.-19-2l) 1 10 opein CC i
s'. us ai rm.ru t Puis;n flat;eup (16-20-20, 16-20-22A, 16-20-22n) 3 IIA Closed SC S
Itr.u-s ui
':1...niup Sy,t em (12-I S, 12-Ill) 1 1
25 Ogien CC S
pc.are ns s:.-anup :.yut em (12-l.ll) 1 45 open CC le til*C l (21-1., J1-lh) 1 1
55 open CC la 4: :1C (Il-IS, 11-16) 1 1
20 Open CC l's l e a s y /!.ci os.d.it V Vacuum Hellef (16-19-llA, 16-19-118) 2 IIA Closed SC l'e li.ias y/Si:cosidairy v.:uinni Itcliet (I t's-19-12 A, 16-19-12 D) 2 IIA Closed Process LTl Coint out Rod liydraulle Hetuin Clieck Valve ( 3-1111 )
NA Open Procesa j
Oo
~
M CD S.
yy5) 115.
4, Amendment flo. 55 is
VYNPS Tabic 4.7.2.b
_PRT!!ARY CO:ITAllefEST IGOMTT0;I V&Yfj_
VA1.VES tioT SIM.1Ecr TO TYPE C I E AXAr.E TfSIS.
Nurber of Pcr.icr Maxinum Aceton on Isolation Operated Valves Operating liornal Initiating Group (tlot e 1)
Valve Identification Inb oa rd Detboard Tim (scc) Pes it ion Si-aal 2
-RilR Return to Suppression Pool (10-39A, B) 2 70 Clnsed SC 2
EllP. I:eturn to Suppression Pool (10-34A, B) 2 120 Closed SC 2
I:llR Dryuell :1 pray (10-26A, B 6 10-31 A, B) 4 70 Closed SC 2
Fillt Sug pression Chaz:hcr Spray (10-33A, B) 2 45 Cl or.ed SC 3
Can t.ii n r.c n t Air Coi. pressor Suction (72-38A, B) 2 20 Open CC 3
.Centair. tent Ai r Sa:rpling Systen (109-75A, D; 1, 2109-76A, B) 30 5
Open CC 4
Fillt Shutdwn Cooling Supply (10-18,10-17) 1 1
28 Closed SC 4
RilR Feactor llead Cooling (10-32,10-33) 1 1
25 Cicsed SC F.reduater Check Valves (2-28 A, B) 2 2
11A 0:> c n Proces Reactor 15..
Cooling Check Valve (10-29) 1.
IIA C1csed Proces S tuadby Liquid Cont rol Check Valves (11-16,11-17) 1 1
tiA Closed Proces Ln N
o CF w
F Amendment. No. 55 136
~
Table 3.ll-1G MAPLHGR, PCT, 0xidation Fraction versus Exposure, Fuel Type 8DP3289 and ?82?32S9 Average Planar Exposure MA?HLGR
?.C.T.
Oxidation (M.Td/ t)
(kv/ft)
(Der-F)
Fraction 200.0 11.2 2126 0.027 1000.0 11.2 2119 0.026 5000.0 11.8 2173 0.030 10000.0 12.0 2185 0.030 15000.0 12.1 2200 0.032 20000.0 11.8 2187 0.031 25000.0 11.3 2120 0.025 30000.0 11.1 2095 O.023
\\
180-n5 Amendment No. 55 1500 170
Table 3.11-2 MCPR OPERATING LIMITS Value of "N" Fuel Tvoe in Exposure Range R3M Ecuation (1) 7x7(2) 8x8 8x8R P8x3R SOC to EOC-2 GWd/t 42%
1.27 1.22 1.27 41%
1.24 1.22 1.24 j30%
1.23 L.22 1.22 EOC-2 GWd/t to EOC-1 GWd/c 42%
1.27 1.23 1.27 41:
1.24 1.23 1.24 j30%
1.23 1.23 1.24 EOC-1 GWd/t to EOC 42%
1.28 1.28 1.30 41%
1.28 1.28 1.30
<40%
1.28 1.28 1.30 (1) The Rod Block Monitor trip setpoints are determined by the equacion shown in Table 3.2.5 of the Technical Specifications.
(2) The current analysis for MCPR Operating Limits do not include 7x7 fuel.
On this basis further evaluation of MCPR operatir, limits is required before 7x7 fuel can be used in Reactor Power Operation.
Amendment No. 55 j}QQ }7l
.