Letter Sequence Other |
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MONTHYEARML20072T0491983-01-31031 January 1983 Suppl Reload Licensing Submittal for Edwin I Hatch Nuclear Plant Unit 2,Reload 3 (Cycle 4) Project stage: Other ML20072T0451983-03-30030 March 1983 Proposed Tech Spec Reflecting Changes to Reactor Core Design for Cycle 4 Project stage: Other ML20072T0371983-03-30030 March 1983 Application for Amend to License NPF-5 Changing Tech Specs to Reflect Changes to Reactor Core Design for Cycle 4 Project stage: Request ML20074A8671983-05-10010 May 1983 Amends 830330 Submittal Re Extension of Malphgr Limits.Eccs Analysis Results Justify Operation of All Facility Fuel Types at Exposures Greater than 30,000 Mwd/St Project stage: Other ML20076E0751983-05-20020 May 1983 Submits GE Info Assuring That crud-induced Local Corrosion Failures Will Not Occur During Cycle 4,in Response to NRC 830519 Request Project stage: Other ML20076E9811983-05-26026 May 1983 Proposed Tech Specs Re Addl Surveillance Requirements for High Reactor Water Level Trip Function & Main Turbine Bypass Valves Project stage: Other ML20076E9671983-05-26026 May 1983 Application for Amend to License NPF-5,proposing Addl Tech Spec Surveillance Requirements for High Reactor Water Level Trip Function & Main Turbine Bypass Valves Project stage: Request 1983-05-10
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[Table view] |
Text
. ._. .-- _ - _ -
TABLE 3.3.9-1 i
i FEEDWATER/ MAIN TURBIE TRIP SYSTEM ACTUATION INSTRUENTATION
- MINIMJM APPLICABLE NTINL FUNCTIONAL UNIT PER TRIP SYSTEM CONDITIONS
- a. Reactor Vessel Water Level-High, Level 8 2 1, when THERMAL POWER 2 25% RATED THERMAL POWER I
1 4
1 1
3/4 3-67 i
8306010371 830526 PDR ADOCK 05000 6
ATTACHMENT 1 NRC DOCKET 50-366 OPERATIfC LICENSE tFF-5 EDWIN I. HATCH NUCLEAR PLANT UNIT 2 PROPOSAL FOR TECHNICAL SPECIFICATION CHAtCES The proposed change to the Technical Specification (Appendix A to Operating License NPF-5) would be incorporated as follows:
Remove Page Insert Page 3/4 3-66 3/4 3-67 3/4 3-68 3/4 3-69 3/4 7-33 B 3/4 3-6 B 3/4 3-6 l
l l
l l
l l
fr #
INSTRtNENTATION 3/4.3.9 FEEDWATER/ MAIN TURBIE TRIP SYSTEM ACTUATION INSTRUPENTATION LIMITIPC C0f0ITION FOR OPERATION l
3.3.9 - The feedwater/ main turbine trip system actuation instrunentation j channels shown in Table 3.3.9-1 shall be OPERABLE with their trip setpoints i set consistent' with the values shown in the Trip Setpoint column of Table 3.3.9-2.
APPLICABILITY:. Condition 1, when THERMAL POWER 2 25% RATED THERMAL POWER ACTION:
With a feedwater/ main turbine trip system actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.9-2, declare the channel inoperable and either place the
, inoperable channel in the tripped condition until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip
/
Setpoint value, or declare the associated system inoperable.
- a. With the number -of OPERABLE channels one less than required by the Minimum CPERABLE Channels requirement, restore the inoperable channel to OPERABLE status within 7 days or reduce thermal power
<,25% Rated thermal power within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
'b. With the number of OPERABLE channels two less than required .by the Minimum OPERA &.E Channels per Trip System requirement, restore at least one of the inoperable channels to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or reduce thermal power < 25% rated thermal power within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />'.
's SURVEILLANCE REQUIRE LNTJ 1
4.3.9.1 Each plant system actuation instrumentation channel shall be demonstrated OPERABLE by. the performance of the CHANEL CHECK, CHANNEL l FUNCTIONAL TEST and CHANtEL CALIBRATION operations for the OPERATIONAL l ' CONDITIONS and at the frequencies shown in Table 4.3.9.1-1.
l ,
4.3.9.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of
' - 'all channels shall be performed at least once per 18 months.
3/4 3-66 l _
l -
I i
. . p .
v
. .t 3
s-n -
e TABLE 3.3.9-2
.. .?s : g FEEDWATER/ MAIN TURBIE TRIP SYSTEM ACTUATION INSTRUENTATION SETPOINTS
,, r
' '( '
ALLOWABLE
, s FUNCTIONAL UNIT TRIP SETPOINT 'VALUE s\
, a. Reector Vessel Water Level-High, Level 8 i 58.0 Inches 6 58.0 Inches i
- See Bases Figure B 3/4 3-1.
is
.1 Il is s t
4 i
4 s
x s
~ k 1
k -
i
,w I s
l.
~
s
, 84 7
b 3/4 3-68 s.
A
\
- - m-m+ 3 w y .- , ,w- = ,v. -w v- -
a- + -w- - -- w- w-
. f.l
/
TABLE 4.3.9.1-1 (Continued)
FEEDWATER/ MAIN TURBIE TRIP SYSTEM ACTUATION INSTRUENTATION SURVEILLANCE REQUIREENTS CHANNEL OPERATIONAL CHAfNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH FUNCTIONAL UNIT CKCK TEST CALIBRATION SURVEILLAPCE REQUIRED
- a. Reactor Vessel Water Level-High, Level 8 NA M R 1, when THERMAL POWER A 25% RATED THERMAL POWER 5
n m
O T
1 r
i a
i
PLANT SYSTEMS 3/4.7.9 MAIN TURBIE BYPASS SYSTEM LIMITING CONDITION FOR OPERATION 3.7.9 The main turbine bypass system shall be OPERABLE.
APPLICABILITY: CONDITION 1,whenTHERMALPOWER225%RATEDTHERMALPOWER ACTION: With the main turbine bypass system inoperable, restore the system to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or determine MCPR to be equal to or greater than the MCPR limit in Specifications 3.2.3 'within one hour or take the ACTION required by that Specification.
SURVEILLATE REQUIREENTS
, 4.7.9 The main turbine bypass system shall be demonstrated OPERABLE at least once per:
- a. 7 days by cycling each turbine bypass valve through at least one complete cycle of full travel, and
- b. 18 months by:
- 1. Performing a system functional test which includes simulated automatic actuation and verifying that each automatic valve actuates to its correct position.
- 2. Demonstrating TURBINE BYPASS SYSTEM RESPONSE TIE to be less than or equal to 0.30 seconds.
i 3 -33 l
O e *b 909 T
NOTE: SCA12 IN INCtES ABOVE VESSEL ZERO WA1TR IZVF.L NOPENCIAftM 800 .- IEICHT ABLW No. VESSEL ZERO READING INSTRIM NT (INCIFS)
(8) 575 +53 YARWAY
~~
(7) 559 +42 G /MAC yggggt (4) 549 +32 m /MAC 723.56 pm- (3) 529.5 +12.5 BARTON (LL1)
= , (2) 479 .18 YARWAY (LL2) 700 -- (1) 370.5 -146.5 YARWAY (LL3)
(0) 313.5 +313.5 YARWAY
~ ~
MAIN STEAM
-640 LINE YARWAY YARWAY M /MAC RARTON 600 --
~577 +60 - - +60 - + 60 - -
+ 60 - -
-575(8) (8) 58 - 5ft *
- 559(7) HPet 6 (7)-42 HI AIARM C
550-3 549(4) (4)- 32 LO ALARM
- 529.5(3) (3) -12.5 LLI
' STRMW 0-0 0 0- ~ RWTOR YARWAY 517 - SCRAM
- DRYER SKIPT 2ERO 3 500 - - 500--
~ FEED I* 4 79(2) . -3R LL2 (2)
WATE R CORE INITIATE RCIC, MAIN Tt" TRINE "465 TMIPS SPRAY HPCI, TRIP RFrIRC.
450-- ptwp3, 400--
-370.5(1) - .146.5 LL3 (1)
-367 150 - - INITIAlt RHR, C.S. ,
START DIESEL, 1 350_ =352.56 il CLOSE MSIV'S AND CONTRIBl% TO A.D.S.
g 313.5 HE IGHT 313.5(0)
PERMISSIVE 3p.
ACTIVE FtTL 25&--
if 8'
200 - -
20e~ g l j RECIRC.
-178.56 -DISCHARc NO2Zu y S UCT ION - 161.5 -
Nor2tz 15 *-
's 100- -
REACTOR VESSEL HATER LEVEL l
50 .
Bases Figure B'3/4 3-1 0--
HATCH - UNIT 2 B 3/4 3-6
- - .- - .- -. .- -.