ML20091K319
| ML20091K319 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 01/14/1992 |
| From: | WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | |
| Shared Package | |
| ML17289A267 | List: |
| References | |
| NUDOCS 9201240105 | |
| Download: ML20091K319 (3) | |
Text
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CONTROLLED COPY EACT,0R COOLANT SYSTEM JET PUMPS LIMITING. CONDITION FOR OPERATION 3.4.1.2 All jet pumps shall be OPERABLE.
APPLICABILITY: OPERATIONAL CONDIT104 b and 2. l ACTION:
With one or more jet pumps inone Able. be in alleast_liOT SHUT 00VN withinf 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. w;W Thtnh tE Wl o 3 re.h iC, acq 8 MUL
~ --
SURVEILLANCEREOUIREMENTS) -
4.4.1.2.1 Eac ode,above required jet putnps shall be demonstrated OPERABLE
.:prdomta=I11 t=E0WER exceed 4ar$+aHalWMoMAL-Swrn-*n+ at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by determining recirculhtien loop flow, total cote flow and diffuser-to-lower plenum differential pressure for each jet pump and verifying -- '
that no two of operating lat3h,the ^
followi,y ollimiillfow condii ions en7enlc.xalu phr- occur when both recirculation
- - ~ ~ ~
(,e n 'il - o g loop L,
, ~ - ~ . . . -
k' a. The indicated recirculation loop flow differs by more than 10% fron. T'IC "*-
the established flow co.itrol valve position-loop flow characteristics 71gyg ,
for two recirculation loop operation.
l b. The indicated total ccre flow differs by more than 10% from the estab-
- iished total core flow value derived from two recirculation loop flow L neasurements,
- c. The indicated diffuser-to-lower plenum differential pressure of any individual jet-pump differs from established two recirculation loop >
operation patterns by mora than,1,0%. 2o g
- 4.4.1.2.2 During single recirculation loop operation, each of the above re-quired jet pumps shall be demonstrated OPEPABLE at least once per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />sy by ._ -- - s
[ ;o$$
I e,, verifying that no two of the following conditions occur _,:,,g ,_
TMb[h.I' Ik ' '#I*)
74TEd r W row. Tt w E R. /
l
' won 'a. The indicated recirculation loop flow in@the operating loop differs ~
88 by more than 10% from the estatlished single recirculation flow gg control valve position-loop flow characteristics.
'$$ b. The indicated total core flow differs by more than 10% from the estab-L gg lished total core flow value derived from single recirculation loop l u flow measurements.
.O ct:ffat.eA l o n: c. The indicated .differenea-to-lover plenum differential pressure of any
@@n. individual jet pump. differs from established single recirculation loop patterns by more than;10%. ,qoy, k Tk. p ew tu. v e, of spec t(ecd m 'i.O 9 u Jap% l M prwided 4,b n e.*o e d l n e. a y.. c C., -cd s ; lbN t r. Li s. Jh d eceA g 2 5 7, d WASHINGTON NUCLEAR - UNIT 2 3/4 4-4 'R AT E b 'T t)E R.4 AL 7tsg r ,
, INDEX s
LIMITING CONDI'i10NS FOR OPERAl10N AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS Standby Service Water 5ystem......................... 3/4 7-1 High Pressure Core Spray Service Water System........ 3/4 7*3 Ultimate Heat 5 ink................................... 3/4 7-4 -
3/4.7.2 CONTROL ROOM EMERGENCY TILTRATION SYSTEM. . . . . . . . . . . . . 3/4 7-5
~
3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM................ 3/4 7-8 3/4.7.4 SNUBBER 5............................. ............... 3/4 7-10 3/4.7.5 SEALED SOURCE CONTAMINATION.... ........... ......... 3/4 7-16 3/4.7.8 AREA TEMPERATURE MONITORING... ...................... 3/4 7-)I IT 3.4.7.9 MAIN TURBINE BYPASS 5YST . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7,)1 o 3/4.8 FLECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES A.C. Sources - Operating............................. 3/4 8-1 A.C. Sources - 5hutdown.............................. 3/4 8-10 i
3/4.8.2 0.C. SOURCES D.C. Sources - Operating............................. 3/4 8-11 D. C. Sourc e s - 5hutdown. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 8-15 i
WASHINGTON NUCLEAR-- UNIT 2 ix Amendment No. 67
t
, CONTROLLED COPY ELECTRICAL POWER SYSTEMS 3/4.8.3 ONSITE POWER DISTRIBUTION SYSTEMS OISTRIBUTION - OPERATING LIMITING CONDITION FOR OPERATION 3.8.3.1 The following power distribution systu divisions shall be energized with tie breakers open between redundant buses within the unit:
- e. A.C. Power Distribution
- 1. Division 1, consisting of:
a) 4160-volt bus SM-7.
b) 480-volt bus SL-71 and SL-73.
c) 480-volt MCC's 7A, 7A-A, 78, 78 A. 78-8, 7F.
d) 480-volt Power Panel PP-7A-B.
e) 120/208-volt 30 Power Panels PP-7A-G, PP-7A-A-A.
f) 120/240-volt la Power Panels PP-7A+A, PP-7A-F, PP-7A-E, and
-7A.
- 2. Division 2, consisting of:
a) 4160-volt bus SM-8.
b) 480-volt bus SL-81 and SL-83.
c) 480-volt MCC's 8A, 8A-A, BB, 88-A, BB-B, 8F.
d) 480-volt Power Panel PP-8A-0.
e) 120/208-volt 30 Power Pancis PP-8A-G, PP-8A-A-A.
f) 120/240-volt 10 Power Panels PP-BA-A, PP-8/.-F, PP-8A-E, and (
PP-BA.
- 3. 0)rision 3, consisting of:
a) 4160-volt bus SM-4.
b) 480-volt 30 Engine & Gen. Aux loads Power Panel, c) 120/240-volt 10 Power Panel PP-4A.
d) 480-volt MCC 4A.
- b. 0.C. Power Distribution
- 1. Division 1, consisting af:
a) 125-volt 0.C. Main Distribution Panel $1-1.
b) 125-volt VOC Motor control Center MC-51-10.
c) 125-VOC Instr. and Control NSSS Bd. Distr. Panel DP-51-1A.
d) 125-VOC r ihA b 1
e ^ Remote Shutdn. Distr. Pnl. OP-51-10.
e) 125-VOC Diesel Gen.1 Dist. Pnl. OP-51-1E.
f) 250-VDC Main Distribution Panel 52-1.
g) 250-VDC Motor Control Center MC-52-1A, Part A and Part B.
n) 124-VOCPowgr{ane{OP-50-A. _
~
- 2. Divihob2f c$nsistin[of: * '
a) 125-volt 0.C. Main Distribution Panel S1-2.
b) 125-volt YOC Motor Control Center MC-51-20.
c) 125-VOC Instr. and Control NSSS Distr. Panel DP-51-2A. ~7 d) 125-VOC Critical Swgs. & Remote Shuton Distr. Pnl. OP-51-?0. ., f e) 125-VOC Diesel Gen. 2 Dist. Pnl. OP-51-2E.
f) :::24-VOC Power Panel DP-50-B.
- 3. Division 3, consisting of 125 volt 0.C. HPC5 distritution pansl. g WASHINGTON NUCLEAR - UNIT 2 3/4 9-16
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