ML20153F298
| ML20153F298 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 08/29/1988 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20153F302 | List: |
| References | |
| NUDOCS 8809070201 | |
| Download: ML20153F298 (10) | |
Text
.
e g @ Ctg g
[f
).,
UNITED STATES
+
NUCLEAR IlEGULATORY COMMISSION 3
W ASHINoToN, D. C. 20655 t
$4.....
PUBLIC SERVICE ELECTRIC A GAS COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-354 HOPE CREEK GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 18 License No. NPF-57 1.
The Nuclear Regulatory Comission (the Comission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Electric &
Gas Company (PSEAG) dated September 2,1987 complies with the standards and requirements of the Atomic Energy Act of 1954, as a
amended (the Act), ar.d the Comission's rules and regulations set j
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; t
C.
There is reasonable assurance: (i) that the activities authorized by 4
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 set forth in 10 CFR i
Chapter I; l
D.
The issuance of this amendment will not be inimical to the comen 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 requirerents have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and
)
paragraph 2.C.(2) cf Facility Operating License No. NPF-57 is hereby l
arended to read as follows:
(2) Technical Specifications and Environmental Protection Plan i
The Technical Specifications contained in Appendix A as revised through j
bendment No.18. and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
PSE&G shall operate i
the facility in accordance with the Technical Specifications and the 4
Envircrr. ental Protection Plan.
g907o201 880829 p
ADOCK 05000354 PNu t
l
. 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/S/
Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 29, 1988 1
h m/
3 4e h/PM PDI-2/D E%f er MC, N'd'"d'M W'
P BC:RSB BC l
GR venbark:tr WButler C*
MHodaes
~
/8
$/ /988 j/j/88
$ /j)/88 t /2L/88 f/f//88
]
C l
2 i
i 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY C0m!$$10N i
vfl 6'(
s Walter R. Butler, Director l
Proje'.t Directorate !.2 i
Division of Reactor Projects I/I!
l Office of Nuclear Reactor Regulation i
i
Attachment:
Changes to the Technical i
Specifications l
Date of Issuant.e:
August 29, 1988 i
l l
r
'f j
t d
'I i.
I I
l 1
f l
I l
I t
E lr i
i i
l r
1 1
1 I
i l
I
, - - - - - - -., - _. - -.. ~. -. _,, -,., _ _, - - -,. -., - -,. _ _
2 l
1 ATTACHMENT TO LICENSE AtiENmENT NO.18 I
1 FACILITY OPERATING LICENSE NO. NPF-57 i
l 00CKET NO. 50-354 i
i Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.
The revised pages are identified by Amendment number and contain vartical lines indicating the area of change. Overleaf pages are 3
provided to daintain document com.pleteness.*
l i
Remove Insert l'
4 1-9*
1-9*
i 1-10 1-10 i
1 3/4 3-59*
3/4 3-59*
l j
3/4 3-60 3/4 3-60 l
1 3/4 3-61 3/4 3-61 l
3/4 3-62*
3/4 3-62*
1 1
8 i
1
}
f I
I t
J J
l l
1 i
j l
1 i
l i
l I
i i
l i
OEFIN!T!CN$
TUR8tNE SYPA$$ $YSTEM RESPONSE TIM (
1.47TheTURBINESYPA$$$Y$fEMRESPONSETIMEconsistsoftwoseparatetimeinter-l vals: a) time from initial movement of the sain turbine stop valve or con.
trol valve until 40% of the turbine bypass capacity is established, ana b) the time from initial movement of the main turbine stop valve or control valve until initial movement of the turbine bypass valve. Either response time may be measured by any series of sequential, overlapping, or total steps such that the entire response time is measured.
UNIOENTIFIED LEAKACE 1.48 UN10thT!FIED LEAKAGE sha11 be all leakage which is not IDENTIFIED LEAKAGE.
l UNRtsTR!cTED AREA 1.49 An UNRESTRICTED AREA shall be any area at or beyond the $1TE 500MOARY
'l access to which is not controlled by the licensee for purposes of protec-tion of individuals free exposure to radiation and radioactive natarials, or any area within the $1TE BOUNDARY used f6r residential quarters or for industrial, commercial, institutional, and/or recreational purposes.
VENTILATION EXHAU$7 TREATMENT $YSTEM 1.50 A VENTILATION EXMAUST ThiAiMENT $YSTEM shall be any sys'.ee designed and l installed to reduce gaseous radiotodine or radioactive natorial in particu-late fore in effluents by passig ventilation or vent exhaust gases through charcoal adserbers and/or HEPA filters for the purpose of reesving todines or particulates free the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Feature (ESF) atmospher'ic cleanup systees are not considered to be VENTILATION EXHAU$f TREATMENT $YSTEM components.
VENT!hG 1.$1 VENTING shall be the controlled process of discharging air er gas free a l
confinement to maintain temper.ture, pressure, humidity, concentration or i
other operating condition, in such a manner that replacement air or gas is not provided or required durin does not imply a VENTING process,g VENTING. Vent, used in systee names, i
1
]
d HOPE CREEK 1-9 Asenament No.14 l
1 FE8 1 1988 I
1 TA8LE 1.1 i
SURVEILLANCE FREQUENCY NOTATION NOTATION FREQUENCY i
S At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
i W
At least once >er / days.
I M
At least once per 31 days.
Q At least once per 92 days.
SA At least once per 184 days.
A At least once per 366 days.
R At least once per 18 months (550 days),
S/U Prior to each reactor startup.
P Prior to each radioactive release.
Z Ouring startup, prior to exceeding 30%
of RATED THERMAL PMR, if not performed within the previous 7 days N.A.
Not applicable.
r i
HOPE CREEK 1-10 Amendment No.
18 I
1 I I k
i g i,5 s
-i g
I.
!8 i
_1.l. )
_I 2 5 i-r r-x w
1 e
2:
j S
- S=
2 3
Sj x4 s
ig g
j 4 ja 2,.
E'.
6 i
i 3
- ,g i
h E
c1 i
a s
s 5g y2-cx cx i
a
,,)
-. g5 2-q_
.a.-
M g
m,3 i
E vive I i v1....
Iv.E..
Ev45a4
- .t.
vilvi5 4*N l
],2 h. h l.18 s
i il iri g
i 2
h
- k..W I
ff.
_t _=
n
.i 2
2 5 :n m-2,*
3 5
g J
3 E
j S
_3.
~-
4 E
_h a
43, 2
- c. 52 ).
_n
- a. _t. ay h
s 39 5 **
56 j:2 SW
.E431
! :i d
!! g !
gg 5
j W h n-M e W-a n l [
E vivi I.i vil aivi I v,4 ai ivrJW>a4
=
w i
vilvi(
,t x
is:.
i s
g2t!1 g
a s
s 1623 g
=
-m I
j=
E s
52 313 B
s i
a I
3 1-
\\
l
}
i
- e 4
- g
~
w m
it 5
a
= a I
j $,
I i-ss 5
1 h t1 lc 3
a s
a w
i s
=
5 s
lass l i 1 1 a
a f
--2; i
=
ar I
s)
I-18 lmsa s
s-fil ill=llill)li !!b am-}. 2 12 !::-}}g!glhgg a 4.. a 1 l g 5 -[5 W w 6 y 4 id34 4 J4 3 44 J4 $ 44 J4 Mi niid Y g 12s 1 m a a a a a a HOPE CREEK 3/4 3 59 Ase m nt M. 15 N. !;33 \\
TABLE 4.3.6-1 CONTROL R00 BLOCK INSTRUMENTATION SURVEILLANCE REQUIRFMENTS Q CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH ^ TRIP FUNCTION CHECK TEST CALIBRATION ') SURVEILLANCE REQUIRED I 1. ROD BLOCK MONITOR a. Upscale NA Z(c)(d) (c) SA la fc C b. Inoperative NA 2 MA 1* c. Downscale NA Z SA 1* 2. APRM l a. Flow Biased Neutron Flux - l Upscale NA 5/U ,M SA 1 b. Inoperative NA 5/U b),M NA 1, 2, 5 5/U(DI,M c. Downscale NA SA 1 I d. Neutron Flux - Upscale, Startup MA 5/U ,M SA 2, 5 m A 3. SOURCE RANGE MONIT045 [ a. Detector not full in MA 5/U ,W NA 2, 5 o b. Upscale NA 5/U SA 2, 3 5/U(b),W c. Inoperative NA 5/U(b),W 2, 5 NA d. Downscale NA .W SA 2, 5 4. INTERMEDIATE RANGE MONITORS 5/Uf a. Detector not full in MA 5/U(b,W A 2, 5 b. Upscale NA b),W SA 2, 5 P c. Inoperative NA 5/U W NA 2, 5 d d. Downscale NA 5/U(b),W SA 2, 5 k 5. SCRAM DISCHARGE VOLUME Water Level-High (Float Switch) NA M R 1, 2, 5** a. [ 6. REACTOR COOLANT SYSTEM RECIRCULATION FLOW 5/U(D) M I ~ a. Upscale NA SA 1 }, b. Inoperative NA 5/UI },M MA 1 c. Comparator NA 5/U ,M SA 1 7. RfACTOR MDivE SWITCH SHUIDOWN TW NA 3 NA 3, 4 -m --r
1 o TA8LE 4.3.6-1 (Contineed) CONTROL R00 BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS NOTES: a. Neutron detectora may be excluded from CHANNEL CALIBRATION. b. Within 24 hcurs prior to startup, if not performed within the previous 7 days. c. Includes reactor manual control multiplexing system input, d. Within 24 hours prior to exceeding 30% of RATED THERMAL POWER, if not performed within the previous 7 days. With THERMAL POWER > 30% of RATED THERMAL POWER. With more than one contrcl rod withdrawn. Not applicable to control rods rencved per Specification 3.9.10.1 or 3.9.10.2. I 1 1 I I 1 l 1 l 4 4 i HOPE CREEK 3/4 3-61 Arendment No. 18 I
INSTRUMENTATION l 3/4.3.7 NONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION LINITING CONDITION FOR OPERATION i i t 3.3.7.1 The radiation monitoring instrumentation channels shown in Table 3.3.7.1-1 shall be OPERABLE witn their alors/ trip setpoints within the specified j limits. APPLICA8!LITY: As shown in Table 3.3.7.1 1. i i ACTION: I l a. With a radiation monitoring instrumentation channel alars/ trip setpoint exceeding the value shown in Table 3.3.7.1-1, adjust the sitpoint to within the 11 alt within 4 hours or declare the channel ir. operable. I b. With one or acre radiation monitoring channels inoperable, take the ACTION required by Table 3.3.7.1-1. ( c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. l l l SURVEILLAhCE RE0VIREMENTS l l I i 4.3.7.1 Each of the above required radiation monitoring instrumentation i channels shall be demonstrated OPERA 8LE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the i I conditions and at the frequencies shown in Table 4.3.7.1-1. l l 1 4 J I 4 i 4 HOPE CREEK 3/4 3 62 i 1 .~ . ~ _ - _ _.._. _ _.. _}}