ML19224B175
| ML19224B175 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/07/1979 |
| From: | Metropolitan Edison Co |
| To: | Mullinix W NRC/IE |
| References | |
| 2102-1.1, TM-0012, TM-12, NUDOCS 7906140161 | |
| Download: ML19224B175 (53) | |
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DOCUMENT NO:
COPY MADE ON OF DOCUMENT PROVIDED BY METROPOLITAN EDISON COMPANY.
U1.491 Wilda R. Mullinix,.NRC 7906140161 3:
190 134
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. CENTRAn Revision 39 03/07/79 THREE MILE ISLAND NUCLEAR STATION UNIT #2 OPERATING PROCEDURE 2102-1.1 UNIT HEATUP Table of Effective Pages Pace Date Revision Pace Date Revision Pace Cate R evision 1.0 10/06/78 15 23.0 02/24/78 8
2.0 05/23/77 0
24.0 06/21/77 1
3.0 01/19/78 6
25.0 06/21/77 1
4.0 03/07/79 19 26.0 06/21/77 1
5.0 03/07/79 19 27.0 05/04/78 9
6.0 08/25/78 14 28.0 10/06/78 15 7.0 08/25/78 14 29.0 12/15/78 17 8.0 08/25/78 14 30.0 05/04/78 9
9.0 10/06/78 15 31.0 01/19/78 6
10.0 10/06/78 15 32.0 03/07/79 19 10.1 10/06/78 15 33.0 12/01/77 5
11.0 11/06/78 16 34.0 03/07/79 19 12.0 11/06/78 16 35.0 03/07/79 19 13.0 11/06/78 16 36.0 02/21/78 7
14.0 11/06/78 16 37.0 12/01/77 5
14.1 11/06/78 16 38.0 01/19/79 18 15.0 08/25/78 14 39.0 01/19/79 18 16.0 03/07/79 19 40.0 12/01/77 5
17.0 10/06/78 15 41.0 05/04/78 9
18.0 10/06/78 15 42.0 12/01/77 5
18.1 10/06/78 15 43.0 12/01/77 5
19.0 08/25/78 14 44.0 01/19/78 6
20.0 08/25/78 14 45.0 11/06/78 16 21.0 08/25/78 14 46.0 01/19/79 18 21.1 08/25/78 14 47.0 10/06/78 15 22.0 02/24/78 8
48.0 10/06/78 15 Unit 1 Staff Recommends Approval Unit 2 Staff Recommends Approval Date Approval Date Approval Cognizant Dept. Head Cognizant Dept. Head Unit 1 PORC Recommends Approval Unit 2 PORC R mmends Approval Date 3!S!M d
Date W
Chairrnen of P0RC f Chairman of FORC I
Unit 1 Superintendent A proval Unit 2 uperintendent Approval I
3 (6dL-DateN/
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Date
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Date Manager Generation Quality Assurance Approval l Y O J $U$-
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n 2102-1.1
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Revision 15 10/06/78 THREE MILE ISLAND NUCLEAR STATION APR 2 3 1379 UNIT #2 OPERATING PROCEDURE 2102-1.1 UNIT HEATUP Table of Contents SECTION PAGE
1.0 REFERENCES
2.0 1.1 Drawings Applicable for Operations 2.0 1.2 Operating Procedures Applicable for Operation 2.0 1.3 Manufacturers' Instruction Manuals 3.0 1.4 System Descriptions 3.0 1.5 Curves, Tables, etc.
3.0 2.0 LIMITS AND PRECAUTIONS 3.0 2.1 Equipment 3.0 2.2 Administrative 6.0 3.0 PREREQUISITES 8.0 4.0 PROCEDURE 8.0 APPENDICES
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Title A
Pre Heatup Checklist - Overall Support Systems 26.0 B
Mode Change - Surveillance Checkoff List (Mode 5 to Mooe 4) 31.0 C
Mode Change - Surveillance Checkoff List (Mode 4 to Mode 3) 38.0 D
Steam Leakage Detection and Correction 47.0 t
si 1.0 190 136
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Revision 0 05/23/77 h
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THREE MILE ISLAND NUCLEAR STATION
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UNIT #2 OPERATING PROCEDURE 2102-1.1 UNIT HEATUP
'i l.0 REFERENCES i
1.1 Drawings Applicable for Operation 1.1.1 Reactor Coolant System, B&R Dwg. #2024.
1.1.2 Makeup and Purification System, B&R Dwg. #2024.
1.1.3 Decay Heat Removal System, B&R Dwg. #2026.
1.1.4 Radwaste Disposal - Reactor Coolant Liquid, B&R Dwg. #2027.
1.1.5 Main and Reheat Steam System, B&R Dwg. #2002.
1.1.6 Bleed Steam System, B&R Dwg. #2003.
1.1.7 Auxiliary Steam System, B&R Dwg. #2004.
1.1.8 Feedwater and Condensate System, B&R Dwg. #2005.
1.1.9 Makeup Water Treatment and Condensate Polishing System, B&R Dwg. #2006.
1.1.10 Steam Generator Secondary Side Vents and Drains Systems, B&R Dwg. #2414.
1.2 Operating Procedures Applicable for Operation.
1.2.1 2101-1.1, Nuclear Plant Limits and. Precautions.
1.2.2 2101-2.1, Nuclear Plant Setpoints.
1.2.3 2101-1.3, Containment Integrity and Access Limits.
1.2.4 2103-1.1, Filling and Venting the R.C. System.
j 1.2.S 2103-1.2, Soluble Poison Concentration Control.
1.2.6 2103-1.3, Pressurizer Operation.
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Y 1.2.7 2103-1.4, Reactor Coolant Pump Operation.
1.2.8 2103-1.S, H Addition and Degasification.
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j 2.0 0
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.Y 2102-1.1 5
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1.2.9 2103-1.9, Reactivity Baltnce Calculations.
hPR 2 3 m7g
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1.2.10 2104-1.1, Core Flood.
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l.2.11 2104-1.2, Makeup and Purification.
.i 1.2.12 2104-1.3, Decay Heat Removal.
I 1.2.13 2l05-1.2, Reactor Protection System.
l.2.14 210S-1.4, Integrated Control System.
1.2.15 2l06-1.1, Main and Reheat Steam.
l 1.2.16 2106-1.4, Gland Steam.
1.2.17 2106-2.1, Condensate.
1.2.18 2106-2.4, Feedwater.
1.2.19 2106-2.5, OTSG Secondary Fill, Drain, and Layup.
1.2.20 2106-3.1, Turbine Generator.
1.2.21 2401-4.4, Removal and Replacement of Manway end Inspection Covers of the OTSG.
1.3 Manufacturers' Instruction Manuals.
Not Applicable.
1.4 System Descriptions.
Not Applicable.
1.5 Curves, Tables, etc.
Figure 1 Reactor Coolant System Heatup Limitations.
Figure 2 Simultaneous OH System /RC Pump Operation Limits for Heatup.
Figure 3 Shutdown Baron Concentrations vs EFPD.
Table 1 Method to Determine Subcritical Neutron Multiplication.
2.0 LIMITS AND PRECAUTIONS y
a 2.1 Equipment.
c 2.1.1 Reactor Cociant temperature, pressure and heatup rates shall j
be maintained within the limits specified in Figures 3.4-2 and l
(RefertoFigures1and2attacheg)Og 3.4-3 of T.S. 3.4.9.1.
3.0
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'l 2102-1.1
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Revision 19 i
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Heatup Rate shall not exceed 50 F in any 1/2 hour period.
ApR 2 3 TS10 2.1.2 The pressurizer.aust not be filled with water to solid e'"
water conditions at any time except as required for system hydrostatic tests.
2.1.3 The pressurizer maximum allowable heatup rate shall be limited to 100 F/hr.
(T.S. 3.4.9.2.a) 2.1.4 The temperature of the secondary coolant in the steam generators shall be > 110 F when the pressure of the secondary coolant in the steam generator is > 237 psig per T.S. 3.7.2.1.
2.1.5 When reactor coolant temperature is less than 525 F, no more than 3 reactor coolant pumps shall be run at one time.
The 4 pump interlock is set at 528 F.
U 2.1.6 Do not exceed a temperature of 200 F or 200 psig pressure in the reactor coolant system until reactor coolant pump seal injection flow is established to all reactor coolant pumps.
2.1.7 Both steam generators shall be operable with a water level between 18 and 390 inches when the plant is in Modes 1, 2, 3, or 4 of operation.
(T.S. 3.4.5) 2.1.8 The temperature differential between the pressurizer and the spray fluid shall be maintained less than 410 F (T.S.
3.4.9.2.b).
2.1.9 If CRA Safety Groups l&2 are withdrawn prior to heatup, observe the following:
(1)
S.P. 2313-SU2 Intermediate Range Functional must be I
performed immediately upon closing CRD breakers.
(2) The shutdown bypass should be initiated ir CRA Groeps 1 & 2 are to be withdrawn, and the high flux trip setraint should be reset to 5,0%.
1?0 139 4.0
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2102-1.1 i
Revision 19 /
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f APR 2 3 (3) Prior to reaching 1820 psig, the shutdown bypass bistable
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setpoint, safety rod groups l&2 should be inserted until the shutdown bypass has been deactivated and the low pressure bistable is reinitiated at 1900 psig.
The high flux trip setpoint should be reset per Tech. Spec. Table 2.2-1 for the number of RCP's in operation when the bypass is cleared.
NOTE:
If any main steam safety valves have been declared inoperable, reset high flux trip setpoint per Tech Spec Table 3.7-1.
2.1.10 For operations below 525 F Tave, maintain the main feedwater nozzles submerged.
(37% to 99% on the Operate Range).
2.1.11 The Nuclear Instrumentation will be continuously monitored during any reactivity addition.
During withdrawal of Safety Groups one and two, subcritical source multiplication will be confirmed according to the following equation or the startup will be terminated until an appropriate evaluation is made.
M=
[
where M = Multiplacation factor SDM1 = Shutdown Margin prior to reactivity change (% ak/k)
SDM2 = Shutdown Margin af ter reactivity change (% a /k).
NOTE:
SDM1 anc' SDM2 are negative vaiues.
See Table 1 for example.
2.1.12 Plot 1/M vs rod position during control rod withdrawal to insure criticality is not achieved on Safety Groups one and two.
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1 Revision 14 h 1
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2.1.13 For normal plant teatup sac cocidown conditions the maximum 1
delta T between the feedwater line temperature and steam
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generator lower downcomer temperature is 440F when using the 1
main feedwater nozzles.
l 2.1.14 If any handholes or manways in either OTSG were opened during the previous cooldown pericd, retorque the bolts for those handholes or manways per Maintenanace Precedure 2401-4.4 prior to commencing plant heatup.
2.1.15 It is permissible to start one Reactor Ccolant Pump outside the Curve 3 of Figure 2 limits, but inside the Curve 4 limits provided that the second pump in that loop is started as scon as feasible, and not to exceed 10 minutes.
2.1.16 To minimize RC Vent Valve noise during RCP Startups and Shutdowns, start RC-P-2A or 2B first, followed by the second pump in that loop. Secure pumps in the reverse order.
2.2 Administrative 2.2.1 The shutdown margin shall be > 2% ak/k when Keff > 1.0 and 1% aK/K when Keff < l.0 with the most reactive rod stuck out.
(T.S.3.1.1.1).
2.2.2 The boren concentration in the reactor coolant systen shall not be reduced unless at least one reactor coolant pump or one decay heat removal pump is circylating reactor coolant at a flow to the RCS of > 2800 gpm (T.S. 3.1.1.2).
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l In addition, while shutdown, when the RC system baron concentration
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is being reduced by more than 30 ppm a 1/M plot versus the
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amount of water added to the RCS must be maintained. Also the i
~j source range counts per second must be recorded continuously f
whenshutdownanddecreasingRCsystemborenconcentration]((]
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2102-1.1 P.evision 14
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08/25/78 APR g 3 nm
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2.2.3 When operating at reactor coolant pressures less than 500 i
psig, the low range reactor coolant pressure instrument must l
be used for operation.
l 2.2.4 When reactor power is less than 10% FP, do not request a printout of the folicwing computer groups unless their operability below 10% FP has been verified:
G_o. #
Description 20 Worst Case Thermal Conditions.
31 Fluid Conditions.
38 Core Average Themal Conditions.
39 Core Map of Themal Conditions.
40 All Themal Outputs.
53 Selected Themal Conditions.
2.2.5 If any Safety Limit (defined in Technical Specification 2.1 and 2.2) is exceeded, the Shift Supervisor shall notify the Station / Unit Superintendent. The reactor shall be placed in HOT STANCBY within one hour. The licensee shall notify the Commission, review the matter and record the results of the review, including the cause of the condition and the basis for corrective action taken to preclude reaccurrence. Operation shall not be resumed until authorized by the Commission.
2.2.6 If, during operation, the autcmatic safety system does not function as required, the Station / Unit Superintendent shall be notified. The Shift Supervisor shall take appropriate action i
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as outlined in.he Tech. Specs. The reporting requirements of T.S. 6.9 shall be followed. Note that this appropriate action may include shutting down the reactor.
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l 2102-1.1 C
i Revision 14 hj 08/25/78 APR 2 3 mg 2.2.7 When a Limiting Condition for Operation (LCO) (defined in Section 3 of the Technical Specifications) is not met, the l
Shift Supervisor shall notify the Station / Unit Superintendent.
j The reactor shall be placed in at least HOT STANDBY within I hour and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> unless corrective measures are completed that permit operation under the pemissible ACTION statements for the specified time
' interval as measured from initial discovery. The reporting requirements of T.S. 6.9 shall be followed.
2.2.8
" Nitrogen pressure should not be applied ta the pressurizer or the reactor coolant hot legs unless the reactor vessel head has been installed and the studs tensioned.
U 0
2.2.9 When Tave is greater than 300 F, debaration to the Tave <300 F curve of Fig. 3 may proceed concurrent with Heatup.
Do not reduce baron below the 300 F curve of Fig. 3.
3.0 PREREOUISITES Initial Each Step When Completed.
3.1 Concurrence has been received from the Engineering, HP/ Chemistry, Operations, and Nintenance Departments that all work necessary for heatup has been completed.
3.2 Source range (CPS) and intermediate range (AMPS) indication available on strip chart recorder on plant control panel.
3.3 Complete Appendix A, Pre Heatup Checklist.
4.0 PROCEDURE i
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Initial Each Step When Completed.
l 4.1 Place all Integrated Control System (ICS) control stations in j
manual and adjust the manual outputs to zero in.accordance i
m 190 1/;3 8.0 i
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2102-1.1
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Revision 15 s
10/06/78 with 2105-1.4. Verify setpoint stations are set as specified g
G79 in 2105-1.4.
4.2 Verify the f;DTT Key Switch and the Pressurizer Electromatic Relief valve switch (AUTO-OFF-ON) are in the AUTO setpoint position.
(This reduces the electromatic relief valve setpoint to 500 psig).
4.3 Verify the following switch line-up at plant control panel 4.
4.3.1 A STM line break F.W. Latching System - Bypass.
B STM line break F.W. Latching System - Bypass.
4.3.2 Control Switches for " Steam From 2A Gen to Emerg Feed Pump", " Steam From 28 Gen to Emerg Feed Pump", " Steam Driven Emerg Feed Pump Turbine", "2A Emerg Feed. Pump",
and "2B Emerg Feedpump" ar~ in PULL-T0-LOCK.
4.4 Verify that feedwater chemistry is in spec.
NOTE:
If the OTSG's were being maintained in wet lay-up, the hydrazine concentration is too high.
Drain the OTSG's down to 30" on the start-up range and refill with in-spec feed water to % 380".
If the hydrazine concentration isn't reduced, it will shorten the in
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service life of the condensate polishers.
4.5 Establish OTSG 1evels between 97% and 99% on the operate range per 2106-2.5.
U NOTE:
For operation below 525 F Tave, maintain the main feedwater nozzles submerged, At the same time, open the by;nss valves (FW-V66A/B) around the feedwater 2
control valve and control GTSG level by using either the lower tube-sheet drains in order to letdown 9.0 I90 144
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g 2102-1.1 Revision 15
.g 10/06/78 through the SG Hot Drain Ccoler to the Heater Drain GI9
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Tank per 2106-2.5 or open Turbine bypass valves to steam down as required.
If water level exceeds 390" (i.e. >100% on the operating range), invoke ACTION statement b of T.S. 3.4.5.
NOTE:
Ensure that locking pins are removed from the following spring hangers: MSH-105, -105, -169, -115, -116, -
170, -125, -126, -171, -135, -136, -172.
4.6 Fill the reactor coolant system in accordance with 2103-1.1, if necessary.
4.7 Before establishing a steam bubble in the pressurizer, insure that the Reactor Coolant Leakage Recovery System is in operation in accordance with 2104-4.6.
NOTE:
The RCS may be pressurized to 300 psig for a preliminary leak check by using the following steps:
1.
CAUTION: The maximum allowable RC pressure for operation of the DH system with no RC pumps operating is 305 psig.
Pressurizer heatup and cooldown rates are limited to 100F/hr.
2.
Energize pressurizer heaters and establish a steam bubble in the pressurizer to give an RC pressure of 300 psig (RC-3A-PI2), which corresponds U
to a pressurizer temperature of 422 F (RC TI).
t 2
3.
Use the DH Aux Spray Isolation Valve (RC-V149) and the pressurizer heaters to control RC pressure as required.
10.0 190 145
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Revision 15 '
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'i 4.
After the leakage check has been completed, use R 2 3 379 2
RC-V149 to reduce pressure to 30 psig and continue with unit heatup as outlined below.
4.8 Energize pressurizer heaters and establish a bubble in the pressurizer in accordance with 2103-1.3, if necessary. Establish the pressurizer bubble at less than 45 psig reactor coolant pressure with mr;>i control of the pressurizer heaters.
Maintain reacte coolant pressure less than 45 psig.
U CAUTION: On 1 exceed a temperature of 200 F for 200 psig pressure in the reactor coolant system until reactor coolant pump seal injection flow is established Per OP2104-1.2 (M.U. & Purif. System).
CAUTION: On the initial pressurization following a Reactor Coolant System Fill, RCP seal cavities must be vented per 2104-1.2.
4.9 Start a makeup pump and establish seal injection flow to all reactor ccolant pumps in accordance with 2104-1.2.
4.9.lVent the RCP Seal cavities if the RCS has been drained or the MU System has been opened since the seal injection was stopped in accordance with 2104-1.2.
4.9.2 Place pressurizer level control in automatic with setpoint at 100" (25%).
,_4.9.3 Establish letdown flow as necessary to maintain pressurizer level at 100" in accordance with 2104-1.2.
4.10 Vent the reactor coolant system in accordance with 2103-1,1, if
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system pressure has been less that 30 psig.
CAUTION: Do not exceed the decay heat maximum pressure as shown on Figure 2.
10.1
O 2102-1.1 Revision 16 11/06/78 4.10.1 Verify both Upper and Lower oil reservoirs for ga2 3M RC-P-1A/B and RC-P-2A/B are at or slightly above the nomal oil levels.
4.10.2 Verify oil reservoirs for RCP hydraulic snubbers RC-U-6A/B and RC-U-7A/B are at approximately the l
i nomal oil levels.
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4.10.3 Verify oil level in RCP oil drain tanks R0-T-1A/B l
is less than half full.
4.11 CAUTION:
The following steps enable application of vacuum to i
the OTSG's during startup, maintain radioactive gas releases to the environment as low as practicable, and at the same time allow the discharge of small concentrations of radioactive gas from the condenser vacuum pumps to be controlled and credited as planned radioactive gas releases.
(1) Prior to proceeding to Step 4.12 accomplish the following:
Insure SV-V22 and SCA/B are tightly closed.
This will maintain gas releases from the vacuum pump discharges "as low as practicable".
(2) Mark VA-R-748 recorder char t as follows if counts go above backgroui.d in Steo 4.12:
" Commenced planned release at "when vacuum was applied to Date and Time OTSG's.
(3)
Nofify Radiation Protection personnel that vacuum application to the OTSG's may cause a planned radioactive gas release from vacuum pump discharge.
Direct Radiation Protection f
personnal to take and analyze the following samples at VA-R-748 in the event the VA-R-748 increases above background when vacuum is applied to the OTSG's in Step 4.12.
190 14,7 11.0
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21u2-1.1 Revision 16 11/06/78 (a) Marinelli Beaker gas samole (VA-R-748).
APR 2 3 m9 (b) Particulate filter sample (VA-R-748).
(c) Charcoal filter sample (VA-R-748).
(4)
In the event VA-R-748 increases above background in Step 4.12, the samples taken in Step (3) above will be taken and analyzed and calculations will be made to determine the total curies of Noble gas and Iodine and particulate I
release to the environment.
The calculated total curies of Noble gas released will be determined by integrating the VA-R-748 recorder trace.
This value will be credited according to HPP-1675. The VA-R-748 particulate and filter sample analysis results will be used to calculate the total Iodine and particulates released and this value will be credited according to 1675.
1 (5) Vacuum application to the OTSG's in Step 4.12 below is to be terminated immediately by closing the steam vents, drains and 5
turo.ne bypass valves, if VA-R-748 recorder trace exceeds 10 This step insures that Tech Soec gas release rates are cpm.
not exceeded and the release is conducted in a planned and controlled fashion.
4.12 Take manual control of the turbine bypass valves at plant control panel 5 and crack open the valves to draw a vacuum on l
both steam generators.
NOTE:
A vacuum must be maintaineo on the steam generators j
a' until reactor coolant temperature is greater than 220 F.
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2102-1.1 Revision 15 3
11/06/78
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Oh 0 73 4.13 Perform the following operations prior to starting heatup.
(Starting RC pumps).
(1) Set high flux trip setpoint to 5.0% per 2303-M6.
(2) Manually reset the shutdown bypars high pressure trip bistable on each channel (4 total) the reactor protective system. This will trip the channel.
(3)
Initiate the shutdown bypass on each channel (4 total) of the reactor protective system.
Reset each channel which assures the shutdown bypass operability of each channel.
NOTE:
This will remove the folicwing trip protection:
1.
Power / Imbalance / Flow 2.
Power / Pump 3.
Low Pressure 4.
Pressure / Temperature 4.14 Verify that the reactor will be > 1% subcritical during heatup and/or deboration by taking boron samples per 2103-1.9.
The boron concentration required to be 1% shutdown with both safety groups ouc is given in Figure 3.
4.15 Place the folicwing on computer trend recorders until 2155 psig and 532 F.
Mark the recorders with date, time, and scale, and every scz.le change and time. When heatup is complete, remove chart paper, date and time and attach to signed off procedure.
This satisfies Surveillance Requirement 4.4.9.1.1 I
and 4.4.9.2.
(1)
Pt. 0397 - Loop B Tcold
(
1 (2)
Pt. 0398 - RC Pressure (3)
Pt. 0389 - Pressurizer Temperature (4)
Pt. 0394 - Loo? A Tcold (optional)
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2102-1.1 i
l Revision 16 NOTE:
During pressurizer auxiliary spray operation,$$Nb@
I373 spray water temperature differential per SP 2311-7.
4.16 During heatup, plot RCS Temperature and pressure on Figure 1 j
every 30 minutes. Mark time of point on plotted curve every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (T.S. 4.4. 9.1.1).
__,_4.17 Pressurize' the RCS to 150 psig to establish RCP seal venting and seal return flow per 2104-1.2.
f l
4.18 Increase reactor coolant pressure to greater than the l
minimum presstre require: rents for two reactor coolant l
l pumps in A loop (See Figure 2 area 6).
4.19 Place the spray valve control switch in the minual position and verify the spray valve is in the closed position as indicat:.d on Panel 4.
CAUTION:
Maintain pressure within the limits of Figure 2 (area 6) with manual control of the pressurizer heaters.
Should reactor coolant system pressure approach the NPSH limits specified for reactor coolant pumps on Figure 2, stop the reactor coolant pumps.
NOTE:
Maintain RCS temperature <200 F to remain in Mode 5 until simuitaneous operation of RCP's and one DHP is no longer required.
4.20 Start RC-P-2A first, and then start RC-P-1A in accordance with 2103-1.4.
4.20.1 Open RC-V138 and V139 (manual valves) to fill the pressurizer
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code safety valve loop seals.
- l. eave open for approximately 10 minutes, then reclose RC-V138 and V139.
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2102-1.1 Revision 16
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11/06/78 4.20.2 Open RC-VI and observe RC pressure.
A pressure decrease
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APR 2 3 n79 indicates RC-V1 opened and pressurizer spray was available.
Close RC-V1.
Record in Shift and Daily Checks (2301-S1) the spray water differential temperature (if any).
4.21 Run RCP's simultaneously with the DH oump for at least 10 minutes.
4.22 After at least a 10 minute run, stop RC-P-1A and then stop RC-P-2A.
CAUTION:
CH-V1 and DH-V2 will automatically shut at (320) psig RCS pressure, causing loss of suction to the DHP.
T-1 14.1 190 m);,
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2102-1.1
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Revision 14 A
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4.23 Using pressurizer heaters, pressurize to within the area
- R23 m i
bounded by area 5 on Figure 2.
4.24 Start RC-P-2B first, and then start RC-P-1B per 2103-1.4.
t
-j 4.25 While maintaining the RCS in accordance with Figure 2 (area S) 1
.j for simultaneous operation of an RCP and DHP, the CRCM's and 0
Hot legs may be vented while RCS temperature is between 100 F and 200 F.
Conduct reventing per 2103-1.1 Para 4.2.
U 4.26 Prior to RCS T e.ceeding 200 F:
c 1.
Containment integrity must have been established per 2311-5.
2.
Appendix B - Mode 5 to Mode 4 checklist shall have been completed.
3.
INSURE the R.B. Purge and Exhaust system is shutdown.
If the R.B. Purge System is to remain in operation insure the purge time while in Mode 4 or above is logged in Log Book in Panel 25.
4.
Verify sodium Hydroxide Tank is lined up with DH-V8A&B closed and DH-V134A&B, CH-V133A&B open.
4.27 Secure the DH systems and place in ES standby, per 2104-1.3.
CAlfTION:
Insure Intermediate Cooling Water is supplied to CRDM's.
4.28 Verify that reactor coolant pressure is greater than the required pressure for control rod drive operation (as shown on Figure 1 and 2).
l 1.
Complete rod programming verification per 2301-51 and 3
i a
2311-3 f f applicable (T.S. 4.1.3.8a) j 4.29 Verify shutdown margin by comparing the present baron c.:ncentration with the curve value from Figure 3.
If the present boron J
i 190 l$}
15.0 i.
17.
2102-1.1 Revision 19 03/07/79 e
concentration is greater than the value of the (< 300 F)
- R 2 3 373 curve of Figure 3, the 1% SD margin is assured.
4.30 Ensure that the following surveillance is current prior to CLOSING the Control Rod Drive Trip Breakers.
.1 2303-M6, Section 6.10, RPS Functional Test
.2 2303-W1 Source Range Functional Test
.3 Ensure S.P. 2313-502 Intermediate Range Functional l
Test is current prior to entering Mode 4 and immediately I
after closing the Control Rod Drive Trip Breakers.
CAUTION: Verify subcritical multiplication per 2.1.11.
Plot 1/M vs Rod position during rod withdrawel to insure criticality is not attained on the Safety Groups.
4.31 Withdraw Safety Groups 1 and 2, IAW 2105-1.9.
4.32 Establish a hydrogen overpressure in the makeup tank per 2103-1.5.
CAUTION: Limit the pressurizer heat up rate to 100 F/hr (1.5.
3.4.9.2.a) and the pressurizer to loop differential temperature to less than 410 F AT.
/
CAUTION: Limit the temperatui e differential between the pressurizer and s;iray fluid to less than 410 F (T.S. 3.4.9.2.b).
4.33 Insure RC pressure is above the minimum for single RCP in a loop operation, Figure 2 curve 3 and start a third reactor coolant pump and commence reactor coolant system heatup.
-h
?
Energize all pressurizer heaters, control the spray valve manually as necessary to maintai pressure within the boundaries of Figure 1.
16.0 fb
2102-1.1 Revision 15 L
10/06/78
./I 4.34 During system heatup compensate for increasing pressurizer /*PR 2 3 1319 level due to the reactor coolant system expansion by adjusting
~
letdown flow as necessary, and diserting letdown flow to the selec.ted bleed tank to maintain makeup tank level betweer.
55-86 inches.
NOTE:
If adequate letdown is no: possible, reduce the seal flow control valve controller setpoint accordingly, nonnal setpoint is %1 gpm.
Do not set less than 24 gpm.
(Low flow alarm setpoint).
CAUTION Do not feed the steam generators unless the difference between the feedwater line temperature and steam generator lower downcomer temperature is maintained at less than a U
440 F.
NOTE:
Continue to maintain. the main feewater nozzles submerged acutlined in step 4.5 above.
4.35 When R.C. temperature is >220 F and both OTSG lower downcomer U
temperatures are greater than 220 F the requirement to maintain a vacuum in the OT5G's is no longer in effect, place the turbine Bypass Valves in automatic.
4.36 When OTSG temperature is approximately 230 F, cycle the main steam traps per 2106-1.1 Appendix C.
NOTE:
If the heat up rate is low, perform Appendix D to attempt to find and minimize steam leakage.
U 4.37 Prior to 250 F in the RCS, ensure oxygen concentration is in spec per T.S. Table 3.4-1.
~
4.38 Prior to RCS T exceeding 280 F, ensure Appendix C, Mode 4 to c
Mode 3 Checklist has been completed except as noted therein.
17.0
~
9
y, 2102-1.1 Revision 15
,i, e
10/06/78
/i!
0 4.39 Af ter 275 F in the RCS and prior to exceeding 450 psig, place the NDTT Key Switch in the 0FF position.
(This restores the electromatic relief setpoint to normal - 2255 psig).
4.40 Prior to exceeding 500 psig RCS press. place c/s's for the noa-operating MUP's in Normal after stop position.
Ensure one c/s for MU-PIB is in pull to lock position.
4.41 When reactor coolant pressure is greater than 700 psig, but prior to reaching 750 psig. place the core flooding system in operation in accordance with 2104-1.1.
CAUTION: Ouring boron concentration reductions flow in the reactor coolant system must be maintained greater than 2800 gpm (T.S. 3.1.1.2).
4.42 Deborate as necessary in accordance with 2104-1.2 and 2103-1.2 but do not go below the (Tav <300 F) curve of Figure 3.
In addition, while shutdown, when the RC system boron concentration is being reduced by more than 30 ppm a 1/M plot versus the amount of water added to the RCS must be maintained. Also, the source range counts per second must be recorded continuously when shutdown and decreasing RC system boron concentration.
4.43 When a steam generator pressure is approximately 150 psig, start a condensate booster pump in accordance with 2106-2,1.
4.43.1 Insure FW-V17A and B are open and vent the feedwater lines thr lh FW-V61A (B) and FW-V62A (B)..
Failure to properly vent lines could result in a FW Latch Signal when the non-operating FW header is placed in service.
g 4.43.2 EF-P-1 Pump Functional Test per 2303-M14A, B or C must be f
satisfactorily completed prior to OTSG pressure exceeding 18.0 I?g ya5 e
gy 2102-1.1 Revision 15(,
10/06/78 800 psig.
If 2303-M14A, B, C has not been satisfactorily gpg completed within the past 31 days, perform this surveillance as soon as sufficient steam is available (steam pressure 8200 psig) but prior to OTSG pressure exceeding 800 psig.
4.44 When RCS pressure reaches 1670 psig ensure the Safety Injection / RCS press low trip Bistables have reset.
b 3
?,
18.1 I S'o,J,o,
j j
3 2102-1.1 l
Revision 14 l
08/25/78 APR 2 3 r35 l l
t 4.45 Prior to reactor coolant pressure reaching 1820 psig, insert
-i j
the safety groups in accordance with 2105-1.9.
4 4.46 Increase reactor coolant pressure greater than 1900 psig and
.l acccmplish the follcwing:
(1) Reset all RPS cabinet bistables that are tripped except the shutdown bypass high pressure bistable.
(2) Place the shutdown bypass switches (4) on each reactor protective panel to the normal position.
CAUTION: Check main steam pressure prior to closing trip breakers. Closing trip breakers will remove the 125 PSI bias from turbine by-pass valves.
(3) Withdraw Safety Groups 1 and 2, verify subcritical multiplication and plot 1/M vs rod position in accordance with 2105-1.9.
4.47 When reactor coolant pressure is greater than 1850 psig, verify that the Safety Injection Bypass Bistables are reset, and the " Protective Function Fully Enabled" lights are lit.
U 4.48 When RCS temperature is greater than 280 F, conduct RCS hydro if required.
CAUTION:
Insure that the leakage cooling water system is in operation to the RCS Drain Tank per 2104-3.3.
4.49 When RC temperature reaches approximately 350 F commence hard 1
bubble degasification by opening RC-V155 and intermittently jogging open RC-V137, if necessary to establish 15 to 45 cc/kg j
H in the RCS, 2
4.50 Place the turbine bypass valve control stations in automatic
.l (if not already in automatic).
i
/P0 I5f 19.0
=
$'k 2102-1.1 i
Revision 14 08/25/78 APR 2 3 mg 4.51 When steam generator pressure is approximately 500 psig, start i
a feed water pump en auxiliary steam in accordance with 2106-2.4.
l 4.52 When reactor coolant pressure increases above 2100 psig, place f
the pressurizer bear.ers and spray to automatic as outlined in 2103-1.3, and complete 2301-M5 if required.
CAUTION: Ensure 2303-M14A,B or C is cc:nplete prior to exceeding 800 psig in OTSG.
4.53 Place the control switches for MS-Vil A and B MS-V207, EF-P2A and B in Normal-After-Stop at 800 psig in OTSG.
4.54 Place the Emergency FW valves, EF-Vil A and EF-llB in AUTOMATIC as follows:
a.
With the MV-Pos switch in "Pos", place the Emergency Feed Water valve EF-VilA, H/A station in Auto by depressing the Auto pushbutton until the " Auto" light is lit.
b.
Repeat step a. above for Emergency Feed Water Valve EF-VilB.
4.55 When steam generator pressure reaches 800 psig, open and cycle those valves listed in 2106-1.1, Appendix C - Steam Trap Checklist.
CAUTION:
If the F.W. Latching System switches are placed in
" LATCH" position this will cause all valves associated with F. W. Latch to go shut.
4.56 With OTSG pressure between 750 psig and 800 psig, complete the following switch lineup at Panel 4 5
A STM line break F.W. Latching System to Normal l
B STM line break F.W. Latching System to Normal i
lb lSL
- U
{
20.0
~
4
- s3 i
2102-1.1 i
Revisicn 14
_[
l 08/25/78 APR 2 3 1979
~
4.57 When RCS tamperature is greater than 525 F, start the fourth 0
t 4.57.1 Reduce OTSG level to the low level limit via the turbine l
bypass valve anciar the hot drain cccler per 2106-2.5.
l 4.58 Rcset tne overpower trip setpoints of the RPS per 2l05-1.2 for the number of RCP's in operation.
l NOH:
If any main steam safety valves have been declared inoperable, reset high flux trip setpoint per T.S.
Table 3.7-1.
4.59 Deborate as necessary in accordance with 2104-1.2 and 2103-1.2 to the baron concentration specified on the 525 F curve of Figure 3.
4.60 Transfer GS from Aux steam to main steam per 2106-1.4, if possible without cooling down.
4.61 Continue heatup to greater than 525 F.
4.62 Conduct red drcp testing if required per 2303-R1 (T.S. 3.1.3.5).
4.63 Conduct a visual inspection or the reactor coolant system for leaks at this time.
4.64 When RC temperature is greater than 525 F, check hangers MSH-105, -106, -169, -115, -116, -170, -125, -126, -171, -135, -
136, -172, to ensure that the hanger setting indicator is aligned with the hot setting button.
If the pointer is not on the hot setting position, readjust the hanger turnbuckle to achieve the proper hanger setting.
Refer to 2102-3.2 Appendix
{
C for proper turnbuckle setting.
L 4.65 Ccmplete 2301-301.
i
/pg /Op 21.0 i
JL
+
2102-1.1
(
i 3
Re. vision 14
[
08/25/78 fjg ; 3 j73
_~
Final Conditions l
The Unit is in Mode 2 and the reactor coolant temperature is equal to i
or greater than 525 F.
Four reactor coolant pumps are in operation. The i
reactor coolcnt systam is at normal operating pressure with heater and spray cartrols in automatic. All ICS control stations are in hand except the turbine bypass valves and EF valves.
NOTE:
Reactor c:r':;it pump cur figuration may be adjusted as directed by the Shift Foreman at this time.
Ensure the RPS nigh flux trip setpoints are prope'r for the RCP combination prior to criticality. The FW startup control valves may be in auto or manual and OTSG level will remain at the low level limit.
L 4
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NO. OF PAGES 3
REASON:
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PDR OTHER C BETTER COPY REQUESTED ON
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C HARD COPY FILED AT:
PDR CF OTHER C FILMED ON APERTURE CARD NO.
I?0 16l
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i.
APR 2 2
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I. .
2102-1.1 I879 -
l Revision 1 05/21/77 1
TABLE 1 Method to Determine Subcritical Neutron Multiolication SDM1 (100 - SDM2) g,SDM2 (100 - SDM1)
~1 where M = Multiplication Factor SDM1 = Shutdown Margin Prior to reactivity change (% ak/k)
SDM2 = Shutdown Margin after reactivity change (% ak/k)
NOTE:
SDM1 and SDM2 are negative values.
2 = M(CR ) where CR2 = new count rate CR j
CR) = initial count rate Examole:
Condition: The reactor is 10% subcritical. 5.3% reactivity is added by withdrawing safety rods. The initial count rate is 10 cps. The reactor is nev 4.7% subcritical.
Calculation:
SDM1 = 10%: SDM2 = 4.7%
10 (100 + 4.7, 10 (104.7) = 2.025 g, 4.7 (100 + 10) 4,7 (110)
CR2 = 2.025 (10) = 20.25 cps.
~
1 25.0 190 162 e
- e
/.
I ;. ' :i W
APR 2 3 mg ?
2102-1.1
{
Revision I 06/21/77 APPENDIX A Pre-Heatup Checklist Overall Support Systems i
No.
Descriotion Initial l
1.
Verify a current r.,rmal electrical system lineup per 2107-1.1 2.
Verify a current Class lE electrical system lineup per 2107-1.2.
L 3.
Nuclear Service river water system is in operation per 2104-3.1 4.
Secondary services river water system is in operation per 2104-3.4 5.
Nuclear Services closed cooling water system is in operation per 2104-3.2.
6.
Secondary Services closed cooling water system is in operation per 2104-3.5.
7.
Instrument and service air systems are in operation per 2104-2.3 and 2104-2.10.
8.
Place one or more circulating water pumps in operation per 2104-3.6.
9.
All the below listed auxiliary systems are in service:
A.
Spent Fuel Cooling - 2104-1.5 B.
Aux. and Fuel Handling Building Ventilation -
2104-5.3/2104-5.2.
C.
Cycle Makeup Pretreatment - 2104-2.1 D.
Demineralizer Service Water - 2104-2.2.
E.
Miscellaneous Support Building HVAC 1.
Control Building HVAC - 2104-5.4.
2.
Service Building HV - 2104-5.5.
3 f
3.
Turbine Building HV - 2104-5.6.
4.
Diesel Building HV - 2104-5.7.
5.
Chlorinator Buildinc '4V - 2104-5.8.
26;0 j
190 163
3d j 2102-1.1 Revision 9 05/04/78 1
APPENDIXd APR 2 3 m3 Pre-Heatup Checklist
[
Overall Support Systems No Descriotion Initial 6.
Coagulator Building HV-2104-5.9 7.
Control Building Area HV - 2104-5.10 8.
Circ. Water Pump House HV - 2104-5.11 9.
Air Intaka Tunnel HV - 2104-5.12
- 10. Fire Pump House HVAC - 2104-5.13
- 11. Mech. Draft Cooling Tower Pump House HV -
2104-5.14 12.
River Water Pump House HV - 2104-5.15.
F.
Solid Waste Disposal - 2104-4.4 G.
Screen Hr.use Equipment - 2104-3.7 H.
Circ Water Chlor. & Chem. Feed - 2104-3.10 I.
River Water Chler. - 2104-3.9.
J.
Mech. Draft Ceoling Tower - 2104-3.8 K
Sump Pump and Drainage - 2104-2.5 L.
Nuclear Plant Sampling - 2104-1.11 M.
Secondary Plant Sampling - 2104-2.8.
N.
Fire Service System - 2104-6.1 0.
Heat Tracing - 2107-1.4 P.
Domestic Water - 2104-2.7 Q.
Sludge Facility & Industrial Waste - 1104-50
~
R.
Turbine Bypass - 2106-1.5 i
f
- 10. Start the turbine auxiliaries and place the turbine on the turning gear per 2106-3.1.
27.0 l
190 164
~.-
y 2102-1.1
~
Revision IE 10/06/78 APPENDIX A Pre-Heatup Checklist AFh r 3 73 3 Overall Support Systems No Oescription Initial
- 11. Start the feed pump turbine's auxiliaries and place both main feed pumps on their turning gears per 2106-2.4.
- 12. Verify a current valve lineup for tha feed system per 2106-2.4.
i
- 13. Verify a current valve lineup for the condensate system per 2106-2.1.
- 14. Start both auxiliary boilers or use Unit 1 Cross-Tie and warm up the auxiliary steam header per 2106-1.3.
- 15. Verify a current valve lineup for extraction steam, feed water heater vents and drains per 2106-1.2.
- 16. Start one condensate pump and cerform the feed water cleanup for both heater trains per 2106-2.1.
i Tra n A Train B 17.
Place at least 2 condensate polishing units in service per 2106-2.2.
18.
Place gland steam system in operation per 2106-1.4.
19.
Establish vacuum in the main condensers per 2106-2.3.
20.
Place condensate chemical feed system in operation per 2106-2.8.
- 21. Open the isolation valves on the turbine bypass system (MS-V-23A & B and MS-V-24 A & 8)
- 22. Complete a vavle lineup on the emergency feed system per 2104-6.3
- 23. Complete a valve lineup on the main steam system per 2l05-1.1.
?
- 24. Place the isolated phase bus duct cooling system 4
in operation per 2106-3.6.
in preparation for Commence purging generator viith C0 25.
Insure seal oil sy$ tem is in operation adding H gas.
2 per 2106-3.3.
1?0 165 28.0
2105 Rev1 APPENDIX A O
Pre-Heatup Checklist
~
Overall Supperi Systems No Description N
~
Ini tia r
~_
Reactor Builhl_ Systems 26.
Place environmental barrier s.*tel in operation per 2104-1.8 27.
Place penetration cooling spm in operation per 2104-1.7.
- 28. Place reactor building venttfon systems in operation per 2104-5.1.
28.1 Verify Reactor Vessel heads are in operation.
PrimarLDort System 29.
Decay heat closed coolingr system is in operation per 2104-3.3.
- 30. Decay heat removal systenn operation per 2104-1.3,
- 31. Place interrcediate coolittem in operation 'per 2104-1.6.
- 32.. Complete a valve 1ineup makeup and purification sys tem per 2104-1.,.
c Verify a current valve bn the nitrogen supply 33.
system per 2104-1.10.
- 34. Complete a valve lineup chemical addition system per 2104-1.12.
- 35. Verify a minimum volume,000 gallons in the reactor coolant bleed t
- 36. Verify OTSG manway andy cover bolts are torqued or retorqued, Sriate, per 2401-4.4, Instion S_ystems
- 37. The following instrumesystems are in the Y
conditions specified bi A. Two source range in, NI-l & NI-2 j
have current tests nd read greater i
than 2 cps.
I 9.0 f
}d6
us-3
.t.
2102-1.1 i
Pevision 9 05/04/78 E 3 1
~
bl / -
APPENDIX A A R 2 3 ;373 Pre-Heatop Checklist Overall Support Systems No Descr10 tion ini tial B.
NI lined up per 2105-1.1 C.
RPS lined up per 2105-1.2.
D.
Verify below listed RPS signal jacks are connected to operating channels.
1.
PC Pressure to NNI 2,
RC Flow to NNI 3.
RC Flow to Computer 38.
SFAS lined up per 2105-1.3.
39.
Nhi lined up per 2105-1.6.
- 40. Seccadary Plant Auxiliary Control System Instrumentation in operation per 2105-1.7.
Locked Valves 41. Verify the status of the plant locked valves per th' locked Valve Book.
42.
Review " Jumper and Bypass Control" Book.
APPENDIX A Checklist Complete:
Signa "re Date
.I 31 0 i
S%
s,.
2102-1.1 3
g ' ',
[
Revision 6 01/19/78 j
i APPENDIX B l
AFR 2 3 g SURVEILLANCE REQUIREMENTS Appendix B data sheets list the surveillance requirements for ascention form Mode 5 to Mode 4.
a.
The INITIALS block for each requirement certifies that satisfactory data for the applicable Surveillance Procedure has been collected within the time interval indicated in the SURV FREQ block and is available for audit.
b.
The DATE SP SATISFIED block shall contain the date of the last satisfactory performance of the applicable Surveillance Procedure.
c.
The NAME, DATE, TIME entries at the bottcm of the MOD" columns signify that surveillance requir'me ccmpliance has been verified and that entry may be made into the specified GPERATIONAL M0]E.
d.
When a Surveillance ProcedJre iS.itablished, the schedule of surveillance relevant to that procedure is a function of that procedure, the responsible supervisor and the Tech Spec Surveillance Program (AP1010).
e.
The pump and valva functional tests are urnally designated as A/B.
The A procedure functionally tests the pun 4s and valves and has a 92 day interval. The B procedure usually chly contains pump testing, and has a 31 day interval.
If the A test v.c performed within t.1e past 31 days, this satisfies the monthly pump test requirement.
c Note however, that if the A test was run 60 days ago (stil, current y
a'-
based on an 92 day intcrval), the pumps must be retested by either another A test or a 9 test to be current within the last 31 days.
i 120 168 i
31 o
2102-1.1 Fevision 19 03/07/79 APPENDIX B
~~
Mode 5 to Mode 4 Page 1 of 8 DATE SP SURV.
RESP 0ti-SATISFIED It!ITIALS FREQ.
SIBILITY SP NO.
TS f10.
DESCRIPTI0ft S,0 OPS 2301-S1 REFER TO 2301-S1 SilIFT AND DAILY CilECKS 7 da OPS 2301-W1 REFER TO 2301-W1 WEEKLY CilECKS 7 DA OPS 2301 'l2 4.8.2.3.2 STA STG BATT CilECKS 230!-M2 4.1.2.1 (b) 31 da OPS attachment 1 &
4.1.2.2 (b)
BOR0fl IllJ VALVE LItiEUP 2A or 2B 4.5.2 (b)
ECCS VLV LIllEUP VERIF 31 da OPS 2301-M7 4.5.3 (b)
(MODE 4: ONE SUB-SYS REQ'D) 31 da OPS 2301-M8 4.6.1.1 (a)
CONTAlflMENT IllTEGRITY
- 4. 6. 2. F( a )
31 da OPS 2301-M9 4.6.2.2 (a)
RB SPRAY SYS VLV L!flEUP VERIF O
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2102-1.1 Revision 19 03/07/79 APPENDIX B i
Mode 5 to Mode 4 Page 3 of 8 DATE SP SURV.
RESPON-SATISFIED INITIALS FREQ.
SIBILITY SP NO.
TS NO.
DESCRIPTION l
Table 4.3-1 MANUAL REACTOR TRIP l
OPS 2313-SU3 Funct. Unit 1 (2 PUMPS OPERABLE) 4.1.2.4 MU PUMP FUNCTIONAL 31 da OPS 2303-M1A or B 4.5.3 (f)
(2 PUMPS OPERABLE) 4.1.2.5 31 da OPS 2303-M2A or B 4.5.3 (fl DHR PUMP FUNCT10flAL (2 OPERABLE )
4.5.2.C (4.5.3)
OPS 2311-5
- 4.6.1.1.a.1 "*"
CONTAINMENT INTEGRITY 4.6.1.3.a (4.6.1.1.b)
(4.6.1.2.e) 4.3.3.1 tab 4.3-3(b) RMS-RB CUAN FutiCTI0flAL 31 da OPS 2303-M9 4.4.6.1 (a)(c)
(ilP-R-227) 31 da IC 2303-M10 4.3.3.7 CilLOR DET SYS FUNCTI0tlAL 31 da OPS 2303-M12 4.6.2.3 (a)
RB CLG UNIT OPERATIONAL 31 da OPS 2303-M15 4.7.7.1 (b)
CONTROL ROOM EMERG VENT CK A or C and B or 0 31 da OPS 2303-M16 4.8.1.1.2 (a)
EMERG DG OPER CliECK (2 OPERABLE) 92 da OPS 2303-M16A and B 4.0.5 EMEPG. D.G. VALVE TESTING CONT BLDG LIQ COOL PMP AND 92 da OPS 2303-M23A 4.0.5 VALVE FUNCT 31 da OPS 2303-M23A or B 4.0.5 CONT BLDG LIQ COOL PMP FUNCT 4.3.1.1.1 IllTERMEDIATE RANGE CllANilEL IC 2313-SU2 Table 4.31-1.10 FullCTIONAL TEST
- Insure the appropriate sections of 2311-5 are current.
'o 4h O
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h,,.,.
......i.
2102-1.1 Revision 19 APPENDIX B Mode 5 to Mode 4 Page 4 of 8 DATE SP SURV.
RESPON-SATISFIED INITIALS FREQ.
SIBILITY SP NO.
TS NO.
DESCRIPTION 4.0.5 92 da OPS 2303-M24A 4.6.2.1 (b)
RB SPRAY PUMP AND VALVES 31 da OPS 2303-M24A or B 4.6.2.1 (b)
RB SPRAY PUMP FullCT 4.0.5 92 da GPS 2303-M25A 4.7.3.2 DNCCW PUMP AND VALVES 4.0.5 31 da OPS 2303-M25A or B 4.7.3.2 DHCCW PUMP FUNCT 31 da OPS 2303-M26 4.1.2.7 BORIC ACID PUMP FUNCT l
92 da OPS 2303-M27A 4.0.5 EF PUMP AND VALVES 31 da OPS 2303-M27A or B 4.0.5 EF PUMP FUNCTI0flAL 92 da OPS 2303-M28A 4.0.5 NSRW PUMP AND VALVE 31 da OPS 2303-M28A or B 4.0.5 NSRW PUMP FUNCTI0ilAL CDTlTBFDG RW B0OST PUMP AllD VALVE 31 da OPS 2303-M29 4.0.5 FUNCT 92 da OPS 2:03-M30A 4.0.5 NSCCW PUMP AtlD VALVE 31 da OPS 2303-M30A or B 4.0.5 NSCCW PUMP FUNCTIONAL 4.6.2.3 (b)
RB EfB G COOL B0OST PUMP 92 da OPS 2x13-M31A and B 4.0.5 AND VALVE FUNCT 4.6.2.3 (b)
RB EMERG COOL B00ST PUMP 31 da OPS 2303-M31A or C 4.0.5 FUNCTIONAL (A & B Pumps) 4.6.2.3(b)
RB EMERG COOL BOOST PUHP 31 da OPS 2303-M31 B or D 4.0.5 FUNCTIONAL (C A 0 PUMPS) 31 da OPS 2303-M32A/B 4.0.5 SF COOLING PUMP FUNCT
~
31 da GPS 2303-H33 4.0.5 SW PUMP AND VALVE FUNCT
]
4.3.2.1.1 tab SAFETY IlifllATFIIilTTATfDN AND 3
31 da OPS 2303-M34 4.3-2 (la,le,2c )
ACTUATION LOGIC FUNCT.
2W
" h.
N N
35.0 cs
...... k
..,s s
2102-1.1 Revision 7 02/21/78 APPENDIX B i
i UATE SP SURV.
RESPON-Page 5 of 8 Mode 5 to Mode 4 SATISFIED INITIALS FREQ.
SIBILITY SP NO.
TS N0.
DESCRIPTION 4.3.2.1.1 tab RB ISOL & CLG/ MAN INITIATION 31 da OPS 2303-H3S 4.3-2 (ld,2a)
ACTUATION LOGIC FUNCT INSERVICE TESTING 0F llVAC 92 da OPS 2303-05 4.0.5 VALVES VALVE OPERABILITY TEST DURING l
92 da OPS 2303-07 4.0.5 COLD SilVT00WN i
4.6.1.1 (b) 184 da OPS 2303-SA2 4.6.1.3 (b)(c)
RB llATCll INLK & AIRLOCK CK 184 da ES 2303-SA4 4.7.5.1 (b)
INTAKE CHANNEL ELEV. VERIF.-
1 18 Ho OPS 2303-R8 4.5.3 (d.3)
ECCS ISOL, INLK & LEAK INSP aaaa air a a i i 1/Ai reacc ir nitT SYS-SOllRCF XFFR
'O O
5 w
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NJ U
JS r 36.0
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..t 2102-1.1 ReYision 5 12/01/77
' ". -}-
4 l
APPENDIX 8 Mode 5 to Mode 4 Page 6 of 3 DATE SP SURV.
RESPON-SATISFIED INITIALS FREQ.
SIBILITY.
SP NO.
TS NO.
DESCRIPTION 18 Mo OPS 2303-R21 4.8.1.1.2(c.2,3,5)
CLASS 1E DIST SYS FUNCT i
18 Mo EL 2303-R22 4.8.2.3.2(c.d)
STA STG BATT-SERVICE TEST 18 Mo OPS 2303-R25 4.7.7.1(c.e)
18 Mo OPS 2303-R26 4.6.2.l(d.1,d.2)
RB SPRAY SYS LEAK MEASURE EMERG DG LOADING TEST 18 Mo OPS 2303-R29 4.8.1.1.2(c.4)
(BOTil DG'S) 5 YRS EL 2303-5Y1
_4.8.2.3.2(e)
STA STG BATT PERF DISC'IG TEST 5 YRS OPS 2303-5Y2 4.6.2.l(e)
RB SPRAY N0ZZLE FLOW CllECK 5 YRS OPS 2303-5Y3 4.6.2.2(d)
NA0ll TK SQL FLOW RATE CK G
D c3 37.0
% =g m m Nj M
- .3 5
4 b
2102-1.1 Revision 18 01/19/79 APPEllDIX B Mode 5 to Mode 4 Page 7 of 8 DATE SP SURV.
RESPON-i SATISFIED INITIALS FREQ.
SIBILITY a N0.
TS NO.
DESCRIPTION l
SEC COOLANT SPECIFIC ACTIVITY 3 da Cll 2304-303 4.7.1.4 tab 4.7-2(1) (SECTI0ft6.1)
SEC. COOLANT SPECIFIC ACTIVITY 184da Cil 2304-3D3 4.7.1.4 tab 4.7-2(2b) (SECTION 6.2) 92 da Cil 2304-01 4.8.1.1.2(b)
DG FUEL TESTillG 184da Cil 2304-SA1 4.6.2.2(b.2)
RB SPRAY NA0ll TK CONC ANAL.
4.7.1.4 tab i
184da Cil 2304-SA3 4.7-2 (2b)
SEC COOLANT SPECIFIC ACTIVITY 184da ES 2305-sal 4.7.6.1.2(a,b)
BIKE INSPECTION
>6 EFP months ES 2305-R2 4.4.5.1 thru 4.4.5.5 OTSG EDDY CURRENT TEST but by 3/28/80 18 Mo 2305-R3 4.8.1.1.2 (c.1)
DG INSPECTION 18 Mo OPS 2305-RS 4.7.8.1 (c)
(YD SNUBBER INSPECTION CD i
a
=Q m
m 38.0
2102-1.1 Revision 18 01/19/79
~
APPENDIX B Mode 5 to Mode 4 Page 8 of 8 i
DATE SP SURV.
RESPON-I SATISFIED INITIALS FREQ.
SIBILITY SP NO.
TS N0.
DESCRIPTION 2 yrs.
after 2313-RS 4.6.1.6.2 RB STRUCT INTEGRITY TEST 4
b 4.6.1.2(a,b,c)
Mo.
2313-R6 4.6.1.6.1 RB INTEG LEAK RATE TEST
<24 Mo.
2313-R7 4.6.1.2 (d,f)
RB INDIV LEAK RATE TEST 18 Mo IC 2303-R3 4.3.2.1.3 ESFAS RESPONSE TIMES RECLAIMED BORIC ACID TANK 31 da OPS 2601-M1 4.1.2.9 TEMP CllAN CllECK 18 Mo OPS 2305-R1 4.5.2 (d2)
18 Mo IC 2602-R10 4.7.7.1 (a)
CONTROL ROOM AIR TEMP CALIB 18 Mo IC 2602-R14 4.6.1.5 CONTAINMENT AIR TEMP CALIB 18 Mo IC 2602-R15 4.6.2.2 NA0ll STOR. TK LEVEL CALIB 18 Mo IC 2602-R22 4.4.6.2 RCS LEAK.ir.: INSTR CALIB ALL TECil SPEC REQUIREMENTS FOR ENTRY INTO MODE 4 llAVE BEEN SATISFIED:
PERFORMED BY:
DATE TIME APPROVED BY:
DATE TIME h
~
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$3 39.0 j
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PAI 9(5 W
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. t-cl02-1.1 i
.F Revision 5 12/01/77 I
APPENDIX C SURVEILLANCE REQUIREMENTS 4
Appendix C data sheets list the surveillance requirements for ascention form Mode 4 to Mode 3.
a.
The INITIALS block for each requirement certifies that satisfactory data for the applicable Surveillance Procedure has been collected within the time interval indicated in the SURV FREQ block and is available for audit.
b.
The DATE SP SATISFIED block shall contain the date of the last satisfactory performance of the applicable Surveillance Procedure.
c.
The NAME, DATE, TIME entries at the bottom of the MODE columns signify that surveillance requirement ccepliance has been verified and that entry may be made into the specified CPERATIONAL MODE.
d.
When a Surveillance Procedure is established, the schedule of surveillance relevant to that procedure is a function of that procedure, the responsible supervisor and the Tech Spec Survefilance Program (AP1010).
n 4o o l90 177
"_o
i'..
2102-1.1 Revision 9 05/64/78
(-A APPENDIX C Mode 4 to Mode 3 Page 1 of 6 DATE SP SURV.
RESPON-l SATISFIED INITIALS FREQ.
SIBILITY SP NO.
J NO.
DESCRIPTION S,D OPS 2301-S1 REFER TO 2301-S1 SilIFT & DAILY CilECKS 31 da OPS 2301-M1 4.3.3.6 POST ACCIDENT MON INSTR CilECKS 4.3.3.5 tab 31 da OPS 2301-M4 4.3-6 (all)
REM S/D MON. INSTR CilAN CilECKS CF TK ISOL VLV BKR POSIT VERIF 31 da OPS 2301-M6 4.5.1 (c)
(WiiEN RC PRESS > 800 PSIG) 31 da OPS 2301-M7 4.5.2 (b)
ECCS VLV LINEUP VERIF RCP Seal Leakoff Check 31 da GPS 2301-M5 4.4.6.2 (c)
(When RCS Press = 2155 I 50 PSIG 4.3.3.5 tab 4.3-6 92 da _
IC 2302-01 4.3.3.6 tab 4.3-10(1)
4.3.3.6 tab 18 Mo IC 2302-Rl.2 4.3-10(4)
RCS OUTLET TEMP CilAN CALIB 4.3.3.5 tab 4.3-6 18 Mo IC 2302-Rl.1 4.3.3.6 tab 4.3-10(6)
RPS-RCS PRESS II/L CilAN CALIB 18 Mo IC 2302-RI.3 4.3.3.5 tab 4.3-6 Re>S-RCS FLOW CilAN CALIB
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2102-1.1
'.'J-Revision 6 01/19/78
,jg; u
APPENDIX C
' ' ~
i Mode 4 to Mode 3 Page 4 of 6 DATE SP SURV.
RESP 0tt-SATISFIED INITIALS FREQ.
SIBILITY SP N0.
15 NO.
DESCRIPTI0ft 7.3.3.6 tab 18 Mo IC 2302-R26 4.3-10 (11)
IIPI-FLOW CHAN CALIB 4.3.3.6 tab 18 Ho IC 2302-R28 4.3-10 (14)
OTSG PRESS CilAN CALIB 4.3.3.6 tab 18 Mo IC 2302-R29 4.3-10 (13)
RB SPRAY PUMP FLOW CilAll Call 8 E6.2 (f) 31 da OPS
-2303-M1A or B 4.05 4.1.2.4-MU PUMP FUNCTIONAL 31 da OPS 2303-M2A or 0 4.5.2 (f) 4.0.5
, DilR PI'MP FUNCTIONAL 4.3.1.1.1 tab RPS CllAfitlEL FUNCTIONAL
~
31 da OPS 2303-M6 4.3-1 (12,13)
(WITil CRD BKRS CLOSED) 4.3.2.1.1 RB PRESS 111 til CilAN AND 31 da OPS 2303-M7 tab 4.3-2 (3a,3b)
ACTUATION LOGIC CIIAN, FUNC.
I, 44.0
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2102-1.1 Revision 18 Ye 01/19/79 i
APPENDIX C Mode 4 to Mode 3 Page 6 of 6 DATE SP SURV.
RESPON-SATISFIED INITIALS FREQ.
SIBILITY SP N0.
TS NO.
DESCRIPTION 18 Mo OPS 2303-R7 4.5.2 (d.1)
DHR ISOL & INTERLOCK CHECK 18 Mo OPS 2303-R8 4.5.2 (d.3)
ECCS ISOL INLK & LEAKAGE INSP.
EFW VALVE ACTUATION 18 Mc, OPS 2303-R18 4.7.1.2 (b)
(OTSG PRESS > 800 PSIG) 4.3.2.1.1 tab 18 Mo OPS 2303-R21 4.3-2 (7.a.2)
CLASS lE DIST SYS FUNCTIONAL EACH PRZR CODE SAF TY VLV CliECK REFUELINL MAINT 2302-R24 4.4.3, 4.0.5 (2 VALVES ODERABLE)
EACll REFUELING MAINT 2302-R27 4.7.1.1 MS SAFETY VLV LIFT TEST 18 Mo IC 2602-R16 4.7.1.3.1 COND. STOR. YK. LEVEL CALIB.
31 da Cil 2304-M1 4.5.1 (b)
CF TANK BORON CONC ALL TECH SPEC REQUIREMENTS FOR ENTRY INTO MODE 3 HAVE OFEN SATISFIED:
PERFORMED BY:
DATE:
TIME:
h Ag0VED tiY:
DATE:
TIME:
m co 46.0 u
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.$d
-; U. ie
- 2102-1.1
[:
Revision 15 10/06/78 i
APPENDIX D l&R 2 3 'U9 STEAM LEAKAGE DETECTION AND CORRECTION j
NOTE:
This appendix may be utilized if steam icakage is suspected due to a low heat up rate.
CAUTION: Any valves left closed by this addenda should be identified in the SF's Log.
1.
Establish a steady heat up rate.
j 2.
Close MS-V23A and observe heat up rate.
3.
If heat-up rate has not appreciably increased in 1/2 hour, reopen MS-V23A.
4.
Close MS-V238 and observe heat up rate.
i I
5.
If heat up rate has not appreciably increased in 1/2 hour, reopen MS-V238.
6.
Close MS-V24A and observe heat up rate.
7.
If heat up rate has not appreciably increased in 1/2 hour, reopen MS-V24A.
8.
Close MS-V24B and observe heat up rate.
9.
If heat up rate has not appreciably increased in 1/2 hour, reopen MS-V24B.
10.
Close MS-V36A, insure MS-V35A is closed, and observe heat up rate.
11.
If heat up rate has not appreciably increased in 1/2 hour, reopen MS-V36A.
- 12. Clo..e MS-V36B, insure MS-V35B is closed, and observe heat up rate.
13.
If heat up rate has not appreciably increased in 1/2 hour, reopen MS-V36B.
- 14. Close MS-V32A, insure MS-33A is closed, and observe heat up rate.
I 47.0 1?0 184
7, 4,
2102-1.1
.. y ' P, -
Revision 15
/4 i
g"f10/06/78 APPENDIX D (CONT'D) i NER 2 3 1319
(
15.
If heat up rate has not appreciably increased within 1/2 hour, reopen MS-V32A.
- 16. Close MS-V328, insure MS-V338 is closed, and observe heat up rate.
17.
If heat up rate has not appreciably increased in 1/2 hour, reopen MS-V328.
18.
Insure FW-P-1A is being supplied by aux steam, and close MS-V218.
19.
If heatup rate does not appreciably increase in 1/2 hour, reopen j
MS-V218.
20.
Insure FW-P-1B is being supplied by Aux. steam, and close MS-V21 A.
21.
If heat up rate does not appreciably increase within 1/2 hour, reopen MS-V21A.
22.
Check position of MS-V17.
During start ups, aux steam should be supplying the turbine gland seal system, and MS-V17 should be closed.
23.
Excessive leakage through the turbine throttle valves should cause the turbine to spin. Main steam isolation valves may be closed if this flowpath exists.
5 s.
48.0 0
$00
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