ML20135H366
| ML20135H366 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 09/09/1985 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Georgia Power Co, Oglethorpe Power Corp, Municipal Electric Authority of Georgia, City of Dalton, GA |
| Shared Package | |
| ML20135H367 | List: |
| References | |
| TAC 56985, NPF-05-A-055 NUDOCS 8509230112 | |
| Download: ML20135H366 (7) | |
Text
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g UNITED STATES NUCLEAR REGULATORY COMMISSION o
O r E WASHINGTON, D. C. 20555
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GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTFORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-366 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 55 License No. NPF-5 1.
The Nuclear Regulatory Comission (the Comission) has found that:
l A.
The application for amendment by Georgia Power Company, et al.,
(the licensee) dated February 15, 1985, as supplemented May 14, 1985, 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 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 Consission'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 requirements have been satisfied.
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. NPF-5 is hereby amended to read as follows:
Pa'leaPapa6 P
4 a
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment 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 of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION r
Jo n. Sto z, Chief erating Reactors anch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 9,1985 4
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ATTACHMENT TO LICENSE AMENDMENT NO. 55 FACILITY OPERATING LICENSE NO. NPF-5 DOCKETNO.50-36p6 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.
Remove Insert 3/4 1-8 3/4 1-8 3/4 3-27 3/4 3-27 e
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i s.
w REACTIVITY CONTROL SYSTEMS 4
j 7
FOUR CONTROL R00 GROUP SCRAM INSERTION TIMES w-
, y 3 ~ ~~.
LIMITING CONDITION FOR OPERATION 3.1.3.4 The average scram insertion time, from the fully withdrawn position, for the three fastest control rods in each group of four control rods arranged in a two-by-two array, based on deenergization of the scram pilot valve solenoids as time zero, shall not exceed any of i
the following:
Position Inserted From Average Scram Fully Withdrawn Insertion Time 46.
0.379 seconds 36 1.162 seconds 26 1.972 seconds 6
3.624 seconds APPLICABILITY: CONDITIONS I and 2.
ACTION:
With the average scram insertion times of the control rods exceeding the above limits, the provisions of Specification 3.0.4 are not applicable and operation may continue provided that:
a.
The contml rods with the slower than average scram insertion times are declared inope.able, i
b.
The requirements.of Specification 3.1.3.1 are satisfied, An analysis is perfomed to detemine that adequate scram c.
i reactivity remains for the slow rod combination, and d.
The Surveillance Requirements of Specification 4.1.3.2.c are i
l perfomed at least once per 60 days when operation is con-tinued with three or more control rods with slow scram inser-t l
tion times; Othemise, be,in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
i l
SURVEILLANCE REQUIRENENTS L
\\
- e, 4.1.3.4 All contmi rods shall be scram time tested from the fully withdrawn position as mquired by Specification 4.1.3.2.
I
' HATCH - tm!T 2 3/4 1 7 l
l
+
EncrNITY mfa00 SYSr!!MS CINIME, RCD f! CRAM ACCIMEA'ItRS i
l t
IJMITDC 0"tDITION POR OPERATION I
3.1.3.5 ul control rod scram acomtlators shall be OPERABIZ.
APPLICFBILITY: CDDITIOt31,2 and 5*
l
{
l N.!8 In CGOITICt6 1 or 2 with one control rod scram acom:1ator a.
l imah1 =, the provisions of Specification. 3.0.4 are not 1
applicable and operation may contirue, provided that within 8 j
hairs:
l j
1.
The inoperable mar =ilator is restored to OPERABLE status, j
or i
2.
'Ihe control rod associated with the inoperable acolunator j
is darimred inoperable and the recuirements of j
Specification 3.1.3.1afesatisfied.
1 Otherwise, be in at least Bor within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
In CIECITICW 5* with a thdrawn control rod scram ami=>1ator inoperable, ft:11y inst the affected control red and electrically aimarm the /.firectional control valves or close the i
withdraw isolation wal e within one haar.
'Ihe provisions of Specifia=*i= 3.0.3 not W ie=hta.
t I
RHtVEIIZAN3 RE3DIRBSNES J
l 4.1.3.5 The control rod ac am acananlators shall be determined OPERABLE:
i I
a.
At Isaat once 7 days by verifying that the pressare and leak detectors er not in the almr=ad condition, and b.
At least once prit 18 mnths by perfonnance of at j
1.
CIgetEL p/ACTICIEL '5BT of the leak detectors, and l
2.
QuesEL 3LIBMfrIDH of the preemare detectors to alarm d
at > 940 psig.
l
'At least the somsmalator associated with each withdrawn control rod.
Not applicable to control rods rumpved per' specification 3.9.11.1 or
- 3. 9.11.2.
t j
j BMCE - tBEIT 2
,j 3/4 1-3 Amendme:nt No.
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+
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+. - - -. -
4 -+ -
--- - ----~~ ~"~-~~~~~~~ ~ ~~~
TABLE 3.3.3-14 (Continued)
N ENERGENCY 00RE COOLING SYSITM AC'IIIATION INS'IRtMNTATION y
g H
MINIMDt NLMER APPLICABLE OPERABIE 01ANDEIS OPERATI0tMI, u
'IRIP RitCTION PER 'IRIP SYSTEN CONDITIONSI
- 3. HIGH PIESSURE 000tJNr IMJECTION SYSTEM a.
Reactor Vessel Water level - Im Im (Imsel 2) 2 1,2,3 (2821 M 92 A,B,C,D)
~
b.
Drywll Presaire - High (2 Ell-N694 A,B,C,D) 2 1,2,3 Cbndensate Storage Tank IeSel-Im (2E41-N002, 2E41-N003) 2(b) (c) 1, 2, 3
~
c.
d.
Suppression O> amber Water level-liigh (2E41-N662B,D) 2(b) (c) 1, 2, 3 e.
Iogic Power Monitor (2E41-K])
1(a) 1, 2, 3 f.
Reactor Vessel Water level-High (Iesel 8) (2B21-N693 B,D) 2 1, 2, 3
- 4. AIJ10MATIC D0 PRESSURIZATION SYSTEM a.
Drywell Presaire - High (Permissive) (2 Ell-N694A,B,C,D) 2 1, 2, 3 u
b.
Reactor vessel Water Ievel - Im Im Im (Ieuel 1) 1 (2B21-N691 A,B,C D) 2 1,2,3 ADS ~ Timer (2B21-Kf52 A, B) c.
1 1, 2, 3 1
d.
ADS Im Water Imvel Actuation Timer (2B21-K754A,B; 2B21-K756A,B) 2 1,2,3 e.
Reactor Vescel Water IeSel-Im (Latel 3) (Permissive) 1 1,2,3 (2B21-N695A,B) f.
Cbre Spray Rapp Discharge Presaire - Iligh (Permissive)
(2E21-N655A,B; 2E21-N652A,B) 2 1,2,3 g.
RHR (LPCI M]DE) Rang Discharge Presaire - liigh (Permissive)
(2 Ell-N655A,B,C,D; 2 Ell-N656A,B,C,D) 2/ loop 1, 2, 3 h.
Control Power Monitor (2B21-KlA,B)
}/ bas (a) 1, 2, 3 5
- g
- 5. IOW IIM Ser S/RV SYSTEM k
a.
Reactor Steam Dome Pressire - liigh (Permissite) 5 (2021-N620A,B,C,D) 2 1,2,3 5
.g i~al Alarm only. When inoperable, verify power availability to the tus at least once per 12 hosrs or declare the system inoperable, g
(b)
Provides signal to IIPCI pJap siction valtes only.
(c)
When either channel of the astomatic transfer logic is inoperable, align HPCI punp aJction to the alppression pool.
g I
IIPCI and AIXi are not req ire <1 to 113 01 EltAllt.M with roar: Lor stoimi ekwar prer:nirn S 150 (mig.
us U1
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TAlli.E 3. 3. 3-2
- eg-EllEllCENCY COHE C4Kil.1litt SYNIEll kC1llATIHil IH!i1Hillitill'AIIitil liEIl'n1Nr i g
' ' N,..
T..R. I..P._ _FllllCTipil Al.l.IHfAlli.E p
TRIP liET!*IllllT val.IIE I.
00HE SP,itA_Y SYSTEli Neactor Vessel Water I.evel - I.aw I.nw I.ow (i.evel 1)
.. a.
b.
-121.S Intlies*
> -121.5 inrlees*
Drywell Pressesre - Nigh Ileacler Steam Dome l'ressiere - 1.ow j l.85 psig 31.85psig c.
el. l.ogic Power Honitor 3 422 psig A
? 422 psigAls A
'A l
HA
.2.
N
' _IJMi FilESSilllE C006. ANT I.Nl.E.C.T.I_ON IKNBE..O_F Nil.R._S_Y_ST._E_l.l litywell Pressure - liigli a.
b.
'I' Neactor Vessel Water f.evel - I.ow I.ow I.ow (i.evel 1) $ l.R'i pals i 1.85 psig
.Ileactor Vessel Shrouil I.evel (i.evel D) - liigli
? -121.5 inrhesA 3 -128.5 luclicsA c.
- t. *. llcact or Steam Dome Pressure-l.ow
? -201 inclies*
> -20 7.luclics A I
s.
i
.licactor Steam Dome Pressure-l.nw 3 422 gesigAA
[422psigA*
I e.
f.
Nilu Piemp Start - Tinie pelay Nelay
?..'125 psig
>,, 325 psig
- 1) Piemps A, 2 anelil
- 2) Pump C in i I sernnils in i i seconals 3
I.ogic Power Monitor 0.5 1 0.5 seronals b.5 1 0.5 seconals flA ilA s
-See liases Figure N 3/4 3-1.
- g_
f AThis trip fisuction shall lee less than as cepeal to 5018 psig.
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