ML20031D457

Station Procedure OP 302,Revision 10, Control Rod Drive Sys

ML20031D457
Person / Time
Site:	Millstone
Issue date:	06/18/1980
From:	Nowell J NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20031D456	List: A01877, Forwards Station Procedures OP 302,SP 631.1,SP 631.2, Sp 631.4,SP 631.11,SP 1051,IC 414c,WP-1-24,CNF-7995-4, CNF-F-FFB & CNF-FF & One Oversize Drawing in Response to NRC .Aperture Card Will Be in PDR ML20031D457 ML20031D461 ML20031D464 ML20031D468 ML20031D477 ML20031D489 ML20031D496 ML20031D502 ML20031D512 ML20031D517 ML20031D534 ML20031D547 ML20031D559 ML20263P607
References
RTR-NUREG-0619, RTR-NUREG-619 NUDOCS 8110130347
Download: ML20031D457 (59)

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{{#Wiki_filter:r APPROVAL: E. J. Mroczka DATE: 6-18-80 Station Superintendent STATION PROCEDURE COVER SHEET A. IDENTIFICATION Number OP 302 4ev. J Title Control Rod Drive System ~ Prepared By J. Howell B. REVIEV 1 have reviewed the above procedum and have found it to be satisfactory. TITLE SIGNATURE DATE hT 7 [M DEPARTMENT HEAD ~ kt h. l S h- / ? C. UNREVIEWED SAFETY QUESTION EVALUA1 ION DOCUMENTATION REQUIRED: .__ __(Significant change in procedure method or scope as described in FSAR) YES [ ] NO CK] (If _yes, document in PORC/50RC meeting minutes) D NIRONMENTAL TMPACT (Adverse environmental impact) YES I J ND DO {31 yes, document in PDRC/SDRC meeting minutes) 3. PORC/SORC APPROVAL PORC/50RC Meeting Number / - f/ - M E. APPROVAL AND IMPLEMENTATION -- The attached proced re is hereby approved, and effective on the dates below: $Flll ? ? Ttation Superintenjent/ Unit Superintendent Appr~oved Date Effective Date SF-3D1 Rev. 3 8110130347 811005 PDR ADOCK 05000245 .P PDR

0F 302 Page 1 key. 10 Date: 7/20/81 CONTROL R0D DRIVE SYSTEM PAGE NO. EFFECTIVE REV. DATE 1 10 7/20/81 jg . 39 . y,29,g3 ~ 3 2D 7/2D/B1 4 1D 7/2D/B1 5 3D 7/2D/El I6 10 7 /2 0/ 81 7 10 7/20/81 8 10 ]!2D/B1 9 10 ~~ 7/20/81 10 10 7/2 0/ 81 11 10 7/20/81 12 10 7 / 2 0/ 81 13 10 7 /2 0/81 14 10 7/20/81 35 ID 7/2D/B1 ID 7/2D/81 17 3D 1/2D/B1 38 2D 7/20/B1 19 10 7/20/81 20 10 7/20/81 21 ID ~ 7 /2 0/ 81 22 10 7/20/81 .23

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10

- 7/20/81 10 7/2D/B1 24 ~ 25 10 7 / 2 0/ 81 26 10 7/20/31 ~ 27 10 7/ 20/81 28 20 7/2 0/81 29 10 7/20/81 30 10 7/20/81 i m

4 OP 302 Page 2 Rev. 10 Date: 7/20/81 i CONTROL R00 DRIVE SYSTEM PAGE NO. EFFECTIVE REV. DATE 31 10 7'/20/81 p2 .10 7/20/81 33 1D 7/20/B1 ~ 34 2D 7/20/81 35 3D 7/20/B1 36 10 7/20/81 9 37 10 7/2 0/ 81 38 10 7/20/81 39 10 7/20/81 40 10 7/20/81 41 10 7/20/81 42 10 7/20/81 43 .1D 7/20/81 39---------. g 45 10 7 /2 0/ 81 45 10 7/2D/B1 M JD 7/20/B1 48 10 7 /2 0/ 81 49 ID 7 /2 0/81 50 10 7/2C/81 .51 10 7 /20/ 81 52 10 7/20/81 53 10 ._. 7/20/31 54 10 7/20/81 55 1D 7/2D/B1 56 30 7/2D/B1 57 2D 7/2D/B1 58 10 7/20/81 l

OP 302 Page ? R:v. 10 Date: 7/20/81 TABLE OF CONTENTS - '- ~ ~ ~ ~ 7.1 Placing the Control Rod Drive System in Service 7.2 Removing the Control Rod Drive System From Service 7.3 Accun.ulator Charging Procedure 7.4 Ccatrol Rod Drive System Venting Procedure 7.5 Control Rod Withdrawal, Single Notch 7.6 Control Rod Withdrawal, tbtch Dyerride 7.7 fontrol Rod Insertion, Single Notch 7.8 Control Rod Insertion, Notch Override 7.9 tontrol Rod Insertion, Emergency Rod In 7.10 Hydraulic Control Unit Isolation 7.11 Control Rod Drive Stall Flow Testing 7.12 Control Rod Drive Accumulator Piston Seal Exercising. 7.13 Control Rod Drive High Operating Temperature Trouble Shooting 7.14 CRD Mechanism Flushing 7.15 Inadvertent Control Rod Withdrawal 7.15 Stuck CRD Collet 1 w-ae eN N*** ,,,m,a b

O r OP 302 Rage 4 Rev. 10 Date: 7/20/81 1. OBJECTIVE 1.1 Describe the operations required to place the Control Rod Drive System in ser.,ce as well 'as charging the Scram Accumulators and venting the Drive System. 1.2 Describe the operations required to withdraw the control rods e ~ using a single notch withdrawal mode or a notch override mode. i 1.3 Describe the operations required to insert the control rods = using a single notch insert mode, a notch overrid mode, or emergency rod in mode. 1.4 Describe the operations requit ed to isolate a hydraulic control unit. 'l.3 Describe the operations necessary to remove the Control Rod Drive System from service. 2.- LICENSE REQUIREMENTS 2.1 Refer to the Millctone Nuclear Power Station Unit 1 Technical Specifications, Section 3.3, Reactivity Control, Subsections A-E, Iages 53-62. ~ ~ ~ ~ ~ ~ ~~ 3. __ FSAR REFERENCES 3.7 Volume 3, Section III, 5.0-5.4,

• Reactivity Iontrol Mechanical Iharacteristics"; 6.0--6.4, " Reactivity Control Stability Iharacteristics.

4. PLANT OPERATING REQUIREMENTS 4.1 The CRD hydraulic system provides the motive force to the drives and the only source of charging water to the accumulators. Consequently, it must be in operation whenever - - - ~ ' ~ the reactor is critical and whenever the vessel is hot to cool %e drives. -4.2 The IRD hydraulic system adds makeup water -to the reactor vessel and provides seal water to Rx recirculation pumps as well as hydrotesting the primary system. The system backup pump provides water to the head spray system.

OP 302 Page 5 Rev. 10 Date: 7/20/81 If the CRD backup pump is out of service during a shutdown 4.3 procedure, the control rod cooling water header flow can be reduced and the o;; crating pump used to supply a limited amount of water to the reactcr head spray system. 5. PREREQUISITES [5.1 4160V System is in operation. OP 341. ~ 5.2 Breakers 14E and 14F are energized. 5.3 4BDV System is in operation. DP 342. '5.4 H.E.1C. F3 is energized. 5.5 Vital and Instrument A.C. System is in operation. 9P 343. 5.6 123 V.D.C. System is in operation. OP 344A. 5.7 Plant Air Systems are in operation. OP 333. 5.8 Paclear Instrumentation System is in operation. OP 401-405. 5.9 Reactor Protection System is in operation. OP 408. 3.10 Condensate storage tank is in service. OP 315. 5.11 Cooling wa' :r supplied to CRD pumps TBSCCW. OP 309. "~ 6. ' PRECAUTIONS 6.1 Do not operate a CRD pump unless it is primed. E.2 Avoid repeated steps or jogs of CRD pump since the heat produced by each acceleration will greatly reduce the life of the pump motor winding insulation. ERD pump operation shall be maintained within the following

5.3 limits

6.3.1 Minimum suction pressure - 18 inch Hg. abs. 6.3.2 Minimum oil temperature - 100 F. 6.3.3 Maximum oil temperature - 150 F. 6.3.4 Maximum Drive Water Temperature - 150 F. I ~~ EJ3.5 Minimum Drive Water Temperature - 40 F. 1 1 Maximum Cooling Water Temperature - 100 F, located at 6.3.6 Turbine Building Secondary Closed Cooling Watei Heat Exchanger. p. _.e me e

OP 302 Page 6 Rev. 10 Date: 7/20/81 6.4 Do not take suction to CRD pumps from Hotwell Reject Line when possibility of condensate high conductivity exists, including ._._. _._ _.._.but met litnited to, unit startup-6.5 The drive withdrawal isolation valve must never be closed while the inlet isolatior, valve is open and the accumulator charged. ~ If a drive should be inadvertently exposed to accumelator [ pressure with its withdrawal isolation valve closed, the high pressures developed will damage drive internals. ~ '7. 1GDCEDURE f 7.1 Placing the Control Rod Drive System in Service L 7.1.1 The Control Rod Drive Hydraulic System is lined up for operation in accordance with checkoff list, OPS Form 302-1. 7.1.2 Ensure closed cooling water flow througe pump oil toolers by feeling the pipes. 7.1.3 Check proper oil levels in the constant level oilers associated with each bearing and also the level in --~ ~ .l reservoir supplying step-up gear assembly. m 7.1.3.1 Outboard level 1/4" below the shaft tenterline. '1.7.3.2 Inboard level 7/32" below the shaft renterline. TIDTE: As long as oil is visible in the glass bottles, additional oil need not be added. 7.1.4 Throttle open No.1 (2) CRD pump discharge valve 301-2A Q01-2B). 7.1.5 Establish communications between the Control Room and the CRD pump room. 7.1.6 On CRP 905, set the followii.g controls: Switch ^ Position

• SERAM VDLUME HDR VENT. A "h0RMAL" SCRAM VOLUME HDR DRAIN" l

~

OP 302 Page 7 Rev. 10 Date: 7 /2 0/ 81 Switch Position CRD FLOW CONT. SELECT"

• A-B (302-BA or Manual Air Valve (Local)

(302-6B) "A-S" " STABILIZING VALVE SELECT" "A-B (302-13A or [ 4302_3B) 1 "CRD DRIVE WATER PRESSURE " Partially Open" IDERDL" 302-B i "CRD ORIVE COOLING WATER " Partially Open" PRESSURE CONTROL" 302-10 NOTE: Check the indicating lights associated with each switch position illuminated. 7.1.7 Verify that all scram valves are reset by noting that -~ the white " SCRAM" display above each rod position tisplay on CRP 905 is extinguished. 1.1.B Verify that 2T) wr=Gators are valved io nonnal, assuring that Accumulator Charging Water Riser valve, "113" and Accumulator Gas Char.ging valve, "lll" are open and Act.umulator Water Cylinder Drain valve, "107", closed. 7.1.9 Place the "CRD FLOW CONTROLLER" (340-1) manual-auto switch in " MAN" and the balance potentiometer CCW for .___. 0% [ Closed) flow control valve indication. 7.1.10 Place CRD PUMP NO. A(B) control switch in the ':RUN" ~ ~ position to start the supply pump. 7.1.11 At the CRD CONTROLLER, adjust the Salance potentiometer to establisti flow at 75 gpm as indicated on FI 340-15. NOTE: The pressure at the accumulator charging header should not exceed 1510 psis. _.._..- 7

i OP 302 Page 8 Rev. 10 Date: 7/20/81 7.1.12 Place the "CRD COOLING WATER PRESS CONTROL" (302-10) Switch in the "0 PEN" or "CLOSE" position as required to establish a cooling water header pressure of 20 - - - - - - psid as indicated on the cooling ~~ water pressure gauge. 7.1.13 Place the "CRD DRIVE WATER PRESS. CONTROL" switch in the "0 PEN" or "CLOSE" position as required to ~~ ~ ~ ~ ~ establish a drive header pressure of 250 psid as i indicated on the drive water pressure gauge. In the IRD pump room, throttle the combined pump discharge valve so as not to exceed an accumulator charging ' header pressure of 1510 psig. 7.1.14 Close the flow control valve for 301-13A-8B and check closed isolation valves for the cut-of-service stabilizing valves, i.e., 301-678 & 301-68B. 7.1.15 Adjust the flow ctatrol valve for 302-13A-8A to produce a flow of 4 gpm as indicated on flow 4 indicator 306-66.

7. 1 15

. Adjust the flow control valve for 302-13A-8B to produce a flow of 2 gpm (indicated by a total flow of 5 gpm as shown on flow indicator 302-66). 7.1.17 Similarly adjust 302-13B-8A and 302-13B-BB to satisfy the same flow adjustments and then mturn to standby 1 status. '7 7 1B Repeat Lleps 7.1.15 and 7.1.17 if necessary. 7.1.19 At this point, any flow not being used to cool the drives will return to the reactor as indicated by flow indicator 340-10 on CRP 905. -7.i.20 Vith condensate demineralizer effluent below 0.1 umho ~ ~ ~ ~ supply the Control Rod Drive pump suction from the flotwell Reject to CST header. 7.1.20.1 Establish approximately 1000 gpm reject flow from Hotwell to CST. 7.1.20.2 Open 1-CH-70A and 1-CN-70C. 1)o not close 1-MW-93 (Supply from CST).

\\ OP 302 Page 9 'Rsv. 10 Date: 7/20/81 7.1.21 Refer to Section 7.4 for venting air from the control rod hydraulic system. 7.1.22 Refer to Section 7.3 for accumulator charging procedures. 7.2 Removing the Control Rod Drive System From Service 7.2.1 NOTE: This system will normally always be in service with probably the only exception being shutdown for refueling. Stop "CRD PUMP A (B)" by placing its control switch to the "STOP" position on CRP 905. 7.2.2 leave system valve alignment and control valve adjustments in the operating position. This will permit immediate restart should a rod or rods tend to drift out. 7.2.3 Equipment to be serviced and conditions of shutdown will dictate valving and equipment isolation. 7.3 -Accumulator Charging Procedure Special Precautions and Limitations -l. --Since gas expansion during initial charging results in low nitrogen temperature, the accumulator charging pressu.e must be set only when the temperature of the nitrogen has reached equilibrium. 2.' At any time a hydraulic control unit is connected to the tontrol rod drive hydraulic system, with 1.he scram Eccumulator charged, the drive withdrawal isolation valve (102) and the scram discharge isolation valve (112) must be opened prios to opeling the drivt insert isolation valve (101). Cor.versely, valve (101) must be closed prior ~~ ~ ~ ~ ~ ~ - - ~ ~~to closing valves (10'2) and (112). SerSusdamagetothe LRD rould result if a reactor scram occurred with valve (101) open and valve (102) or (112) closed. 7.3.1 Verify that Control Rod Drive System is in nperation as per Section 7.1. t 1 ( --,r

o OP 302 Page 10 Rev. 10 Date: 7/20/81 s 7.3.2 Close the drive insert isolation valve (10i) and the drive withdraw isolation volve (102). Pay particular attention to Special Precaution 2. 7.3.3 Close the charging header inlet valve (113) to the eccumulator to be charged. 7.3.4 Connect drain hose to threaded conn. on valve (107). -Slowly crack open the accumulator vent valve (107) .and discharge the water accumulator. The accumulator is fully discharged when gas pressure, as shown on the accumulator pressure gauge, remains constant. ~ This indicates that the piston in the water accumulator has reached its mechanical stop. 7.3.5 fully close the gas charging inlet valve (111) on the instrumentation block. 7.3.6 Loosen the nitrogen charging connection cap (P6) and allow gas pressure to bleed from the instrumentation block. 7.3.7 Remove the cap from connector P6 and connect the gas _ _ charging line to the instrumentation block. 7.3.B Slowly open the nitrogen bottle shutoff valve and adjust the pressure regulator to provide the proper charging pressure per attached pressure-versus-ambient-temperature curve, Appendix 2. 7.3.9 Slowly open the gas charging inlet valve (111) and allow accumulator pressure to slowly increase as -indicated on the accumulator pressure gauge. By permitting the nitrogen to enter slowly, it will tend to reach equilibrium temperature and establisn the desired charging pressure more rapidly. 7.3.10 h en correct pressure is attained, close the bottle -shutoff valve end then close the gas charging inlet valve (111). 7.3.11 Bleed pressure from the gas charging line using the charging line vent valve until the accumulator pressure gauge shows zero pressure. t

l t OP 302 Page 11 Rev. 10 Date: 7/20/81 7.3.12 Remove the gas charging line from the instrumentation block and re, lace the cap on connector P6. Insure n i .tk cap seals tightly. 7.3.13 Open the gas charging inlet valve (111) and observe that the charging pressure is shown on the accumulator prcssure gauge (131). This will also .. _.. _ ____._ _ _ _.__ ' place pressure switch 130 and level switch 129 in ~ service. 7.3.14 With the accumulator vent valve (107) cracked open, slowly open the charging header inlet valve (113). When all air has vented, close the vent valve (107). 7.3.15 Allow the piston in the water accumulator to compres= the gas charge to double the value of the initial nitrogen charge (approximately 1150 psig as indicated on the accumulator pressure gauge). CAUTION: AFTER APPR0XIMATELY 30 MINUTES, RECHECK THE TRE550RE TNDICATED I)N ~THE ACCUMULATOR PRESSURE GAUGE AND VERIFY THAT IT REMAINS - -~~ -- - ~~~~ CONSTANT AFTER THE NITROGEN HAS COOLED. IF ~' ~~ AFTER THIS INTERVAL PRESSURE EXCEEDS 1150 PSIG, LOOSEN THE CAP ON CONNECTOR P6 AND SLEED EXCESS PRESSURE. EXCESS ACCUMULATOR PRESSURE COULD RESULT IN INTERNAL CRD DAMAGE IN THE EVENT OF A REACTOR SCRAM. 7.3.16 To return the CRD to service, reopen the is~olation valves in the following order: 102, then 101. 7.4 Control Rod Drive System Venting Procedure 7.4.1 Verify that the hydraulic system is in service and 1 that pressures and flows are properly adjusted.

7.4.2 CAUTION

VATER DRAINING FROM THE CRD SYSTEM IS PDTENTIALLY CONTAMINATED AND SHOULD BE MONITORED FOR RADIATION. ALL NECESSARY PROTECTIVE MEASURES MUST BE TAKEN FOR DEALING WITH A POTENIIALLY CONiAMINATED l LIQUID.

i OP 302 Page 12 R:v. 10 Date: 7/20/81 i Crack open vent valves at hydraulic supply system equipment and header piping high points. ..Sleed all air from system starting at the pump and continuing in sequence downstream. NOTE: The amount of venting required will depend on how extensively the system has been drained. 7.4.3 Vent the control rod drives as follows: 1 1.4.3.7 At the UD valve area, select the drive to te vented and verify it is valved into service. 7.4.3.2 At the CRD Vent Valve Nest, locate the selected drive insert and withdraw line vent valves. Check the' inse* t line vent isolation valve shut, remove the vent plug and connect the venting hose. Run the hose town into the collection trough. i 7.4.3.3 Establish communication with the Control ~~~~~~ - ~ Room and have the Operator insert the drive to " FULL IN" using a continuous insert signal. CAUTION: IF THE VENT PIPlNG BECOMES EXCESSIVELY WARM, REDUCE THE BLEED FLOW RATE. ~7.4.3.4 Have the Control Room Operator maintain the j insert signal and crack open the insert line vent isolation valve for 1 minute to completely bleed the line. Then close the valve. 7.4.3.5 In the Control Room, maintain a continuous insert signal for 3 minutes to flush the 4 rive. 7.4.3.5 Remove the venting hose and replace the j vent plug. Check for ti_qhtness and make sure there is no evidence of leakage. k

i i OP 302 Page 13 Rev. 10 Date: 7/20/81 s 7.4.3.7 Check the selected withdraw line vent isciation valvo shut, remove the vent plug - ~ ~ ~ ~ ~ ~ ~~ ~~ and connect the venting hose. Run tha hose ~ ' - down into the collecting trough. 7.4.3.8 In the Control Rooa, have -the Operator qply.i centinAa:, withdru :sigiul' to the ,/ ~ ~ drive. When,the drive stops moving, either at "fillt DUI" or any other notch, crack open the withdraw line vent isolation valve for ; minyte to Nined I.he line. Th.a close the valve. NOTE: The above tim.s are sufficient to completely fill the piping and drive at r.ormal insert and withdraw flow rates. If the observed flow rates are 'ess l'un normal, increase the vent and _ flush '.imes proportionately. 7.4.3.9 Remove the venting hose and replace the vent plug. Check for tightness and make sure thr re is no evidence ci leakagn. 7.4.3.10 Jn the Control Room, insart the drive to

• FDLL 1N"..

'7.3 r.m'.. O id Withdrawal % U.:.h N'1 CIAL PREREQUISIfE5 1. Mode switch must not be in the shutdown position. 2. R.W.i4. nust to operable. 3. Control rod withdrawal interlock circuit must be ener.gized (insures neutron monitoring and the components of the scram system are operable). 4. Cequential timing circuit musi,'.a operable. SPECIAL PRECAUTIDNS l 1. Moniter the rod position indicators during all pe,15d, oi

• diration of abnorr.:al i od notion.

! m.i.;n % t

) OP 302 Page 14 Rsv. 10 Date: 7/20/81 Abnormal rod motion is defined as motion in the wrong direction, motion when no motion is intended or motion of a Tod not selected. 2. To reduce the severity of thermal cycles imposed on the CRD the temperature should be allowed to stabilize for about three minutes following its withdrawal for a hot l_. test scram. 7.5.1 Check the rod out " PERMISSIVE" indicating lamp illuminated and the " ROD POWER" switch "0N". 7.3.2 Select the particular rod to be withdrawn by l momentarily depressing the pushbutton on the rod-select pushbutton matrix. Observe that the pushbutton illuminates and the rod selection indicator above the position display for the selected Tod is illuminated. NOTE: The control circuit is now set up to supply power to the selected directional control valve solenoids when the rod movement control switch is activated. IAUTION: CONTINUOUSLY MCNITOR NUCLEAR INSTRUMENTATION DURING RUD i!DVEMENT. 7.5.3 Turn the " Rod Movement Control Switch" to the " Rod Notch Out" position momentarily and release (sprin_g return to "0FF").

7. 5. 4 Approximately 8 seconds from turning the control switch, the cycle should be completed and the rod settled in the next notch out (6" from previous position).

Dbserve that rod is latched in the even numbered positions and that it is in the ' latched ~ position before the settle light goes out. 1.5.5 The timer automatically resets for the next operation if switch is returned to *0FF". 7.3 Iontr61 llod Withdrawal, Notch Dverride SPECIAL PREREQdISITES !(

I OP 302 Paga 15 Rev. 10 Date:7/20/81 1. Same as 7.5. SPECIAL PRECAUTIONS .l. Same as 7.5. Check the rod-out " PERMISSIVE" indicating lamp 7.6.1 illuminated and the rod select power switch "0N". 7.6.2 Select the particular rod to be withdrawn by. - momentarily depressing the pushbutton on the '/ rod-select poshbutton matrix. Observe that the pushbutton illum.inates and the rod-selection indicator above,the position display for the selected rod is illuminated. f CAUTION: REACTIVITY INCREASE MAY BE SIGNIFICANT AND WARRANTS THAT PARTICULAR AiTENTION BE DIRECTED TOWARD THE NUCLEAR INSTRUMENTATION. Turn the " Rod Movement Control Switch" to the " Rod 7.6.3 Out" position and also the " Rod Out Notch Override" switch to the " Notch Override" position simultaneously. The rod will continue to withdraw as lon.g as both switches are held in those positions. As soon as either control switch is released, the 7.5.4 sequential timer will complete its cycle and the rod should settle into an even notch position. Observe that the rod latched before the settling light goes out. -7. 7 Control Rod Insertion, Single Notch SPECIt'_ PREREQUISITES 1. Same es 7.5. SPEt1 A1. PRECAUTTONS 1. Same as 7.5. .2. Nomal drive is 250-390 PSID. If the CRD will not insert witfi normal system drive . pressure under the piston, it should be declared inoperable and no further attempt should be made to move the drive unless authorized by the Unit Superintendent. i y ay e e p w W.-

4l i OP 302 Page 16 Rev. 10 Date: 7/20/81 Such a CRD should be electrically disarmed and hydraulically isolated to preclude the possibility of inadvertently scramming the CRD. Scramming a CRD having a l separated collet retainer tube would result in unnecessary damage to the drive. 7.7.1 Check the " Rod Power" switch "0N". "~ ^ ~ ~ ~ ~ ' ~ ~ ~ ~ - -- 7. 7. 2 Select the particular rod to be inserted by inoment arily depressing the pushbutton on the rod-select pushbutton matrix. Observe that the .pushbutton illuminates and the rod selection indicator above the position display for the selected rod is illuminated. 7.7.3 _ CAUTION: CONTINUOUSLY MONITOR NUCLEAR INSTRbMENTATION DURING R00 MOVEMENT. Momentarily move the " Red Control" switch to " ROD-IN" and then release the switch. Observe that the green " INSERT" indicating light comes on following switch Observe that the amber " SETTLE" 1,ight movement. comes on approximately 3.0 seconds after switch movement and remains on for approximately 5.2 seconds. NDH: The rentrol red will actually travel beyond the notch position but will then settle into a notch and complete the cycle. 7.7.4 Observe that the rod latches in the next even-numbered position before the " SETTLE" light goes out. ~~

7. 8 Control Rod Insertion, Notch Override

_SPECIAL PREREQUISITES 1. Same as 7.5. SPECIAL PRECAUTIONS 1. .Same as 7.5. 2. 1)o not exceed 265 PSID. 7.B.1 Check the " Rod Power" switch "DN". l, 7.B.2 Select the pLrticular rod to be inserted by somentarily depressing the pushbutton on the l l

s OP 302 Page 17 Rev. 10 Date: 7/20/81 rod-W ect pushbutton matrix. Observe that the ] pus. ar.on illuminates and the rod selection -... indt ator above the position display for the selected _.-e_.. _. l rod is illuminated.

7.8.3 CAUTION

CONTINUOUSLY MONITOR NUCLEAR INSTRUMENTATION DURING R0D MOVEMENT. [- . Hove and hold the " Rod Control" switch in the " ROD-IN" position. Release the switch to the "0FF" position one digit before the desired notch position is reached. 7.8.4 Dbserve that the green " INSERT" indicating light comes on following switch movement and remains on for the otration of rod insertion.

7. 8. 5 Observe that the rod latches in the desired even-numbered position before the " SETTLE" light goes out.

7.9 Control Rod Insertion, Emergency Rod In SPECIAL PRECAUTIONS 1. Normal drive is 250-390 PSID (refer to Appendix 1). i ~ ~ ~ ~ ~ ~ ~ - NOTEi - The emergency rod-in mode is provided for control rod ~ ~ ~ ~~~ ~ insertion in the event of a malfunction of the timer switch or any other device in 1.he select-in or rod-in circuits. 7.9.1 Check the " Rod Power" switch "0N". 7.9.2 Select the particular rod to be inserted by momentarily depressing the pushbutton on the rod-select pushbutton matrix. Observe that the pushbutton illuminates and the rod selection indicator above the position display for the selected rod is illuminated.

7.3.3 CAUTION

CONTINUOUSLY MONITOR NUCLEAR INSTRUMENTATION DURING R0D MOVEMENT. Nove and hold the rod control switch in the "B! ERG ltDD-IN" position until the desired notch position is reached. Then release the. swit-h to the "DFF" b position. w p e g mo mwm _ eM 46 =-W* F y a

OP 302 Page 18 Rev. 10 Date: 7/20/81 7.9.4 Observe that the green " INSERT" indicating light comes on following switch movement and remains on for the duration of rod insertion. 7.9.5 Observe that the rod latches in the desired even-numbered position. EMERG ROD-IN" stops when switch is released. Reset rod drift light and alarm. / 7.10 Hydraulic Control Unit Isolation NOTE: The following procedure isolates flow of cooling water from the HCU to the CRD. Sustained loss of cooling water when the reactor is at operating pressure and temperhture will shorten the maintenance l I life of the CRD seals. 7.10.1 Fully close the isolation valves in the insert riser I (101) first, then close the withdraw riser (102), charging riser (113), scram discharge riser (112), cooling water riser (104), drive water riser (103) and exhaust water riser (105). 7.10.2 Fully close the isolation valve (116) in the scram valve pilot air line (scram valves may open due to ~ ~ ~ air leakage). 7.')D.3 Dpen the scram valves by either. a. Dive that rod a me.aentary scram signal from CRP 916, then place the toggle switch back to normal and verify scram valves open, or b. Pull fuses on RP5 test panel to de energize scram pilot air valves (117, 1]B). CAUTION: This water is contaminated. 7.i0.4 Connect drain hose to threaded connection on valve 1 07. Carefully open -the water accumulator drain - valve (107)1.0 discharge the water Trom the acca,ulater. H R ERD pumps are shutdown, fully close 107 when il a u t.er has drained..If the CRD pump is running, permit valve 107 to remain open to drain possible ( mF

l OP 302 Page 19 Rev. 10 Date: 7/20/ 81 leakage through the charging water riser isolation valve. 7.10.5 Electrically isolate the HCU from the RMCS if required. 7.10.6 Discharge the gas side of the accumulator as follows: 7.10.6.1 Close the cartridge valve (111) on the accumulator instrument block. 7.10.6.2 Remove the charging connector (P6). 7.10.6.3 Throttle open the cartridge valve (111) to discharge through P6. 7.10.6.4 Ensure the accumulator is de pressurized. 7.11 Control Rod Drive Stall Flow Testing 1. Objective 1.1 This procedure provides a guide for trouble shooting control rod drives and their associated hydraulic control units. 2. References 2.1 GEI-92809, Manual I-G-1-16 2.2 GEI-92807A, Manual I-G-1-18 2.3 gel-92808A, Manual I-G-1-19 2.4 IiEK-39534 2.L Nillstone Technical Specifications 3. Prerequisites 3.1 Permission from the Shift Supervisor for authorization to commen e testing must be o'btained prior to testing. 4. Precautions 4.1 All procedure steps shall be coordinated with the Eontrol Room Operator. 4.2 Technical Specification requirements shall be met at all times during testing. 4.3 Nuclear instrtmentation shall be continuously soniinred 4uring testing. ( 1 l

OP 302 Page 20 ~ Rev. 10 02te: 7/20/81 4.4 Testing shall be performed on one CRD unit at a time. 4.5 To prevent possible drive <1amage in the event the drive is scrammed during isolation or clearing, observe the following: 4.5.1 When isolating a control rod drive,-close the insert header isolation valve 101 before closing the withdraw header isolation valve 102. 4.5.2 When clearing an isolated drive open the 1D2 valve before openin_g the 7D1 valve. frocedure 7.11.7 llecord the t.te on Data Sheet, T)P5 Torm '302-2. 7.11.2 Adjust the drive water pressure to 260 + 3 psig and i record the pressure on the data sheet. (Stall flows measured at other drive water pressures have little or no value when drive trouble shooting.) NOTE: It is important that the drive water pressure be maintained at 260 psig throughout stall flow testing. 7.11.3 Withdraw Stall Flow Testing 7.11.3.1 The withdraw stall flow test is performed to determine the condition of the internal drive seals and can be used to detect leakage past the 121 and 127 valve on the HCU. 7.11.3.2 The test can be performed at any rod position. 7.11.3.3 With the rod at position 48 it is ready to test as is. 7.11.3.4 If the rod is at any position other than 48 the test can be performed by electrically disconnecting the insert directional control valve {123) at the HCU. With the 123 valve disconnected, application of a l ( notch override signal will not result in

E. OP 302 Page 21 Rev. 10 Date: 7/20/81 i drive withdrawal because the insert signal required to unlock the collet fingers will 7.11.3.5 The withdraw stall flow test is performed by applying a notch out override si'gnal to the CRD while reading the drive water flow 7.11.3.6 To perform a withdraw stall flow test on a IRD proceed as follows: 7.71.3.7 Istablish ccmmunications between the Control Room and the CRD-HCU's involved in the testing. J.J1.J.3 At the reactor control panel select the drive to be tested. 7.11.3.9 At the HCU electrically disconnect valve 123 if required by Step 7.11.3.4. 7.11.3.10 Perform test per Step 7.it.3.5, record the drive water flow on Data Sheet, OPS Form 302-2. (The initial test is recorded as ~ Stall Flow 41..) 7.11.3.11 If Flow iP1 < 3.5 GPM, the drive perfomance j is considered satisfactory. s 7.11.3.11.1 Restore the rRD per Step 7.11.5. 7.11.3.11.2 Mark the " Drive Performance ~ ~ Satisfactory" line on Data Sheet, OPS Form 302-2. 7.11.3.11.3 Further stall flow testing is not required for a drive with flow < 3.5 GPM, proceed f

with testing 4f other <fri,"es as required.

7.11.3.12 If flow #1 > 3.5 GPM, exercise the drive j by notching the rod in and out, then repeat Step 7.11.3.10, record the observed flow on

OP 302 Page 22 Rev. 10 Date:7/20/81 Data Sheet, OPS Form 302-2, as Stall Flow

1. 2.

--- 7.T.3.13 Compare Flow #1 with Flow #2. 7.11.3.14 If the flow decreased from #1 to #2, repeat Step 7.11.3.12 until a constant flow is achieved. Record the constant flow on Data Sheet, OPS Form 302-2, Stall Flow #3. NOTE: A decrease in flow is an indication that air was in the drive. The drive will purge out any remaining air allowing a better measurement of stall flow. 7.11.3.15 If Flow #1 = Flow #2, proceed to Step 7.11.3.16. 7.71.3.16 Isolate the drive at its HCU by closing 101 and 102 (Ref. Precaution 4.1), then repeat the withdraw stall flow test per Step 7.11.3.6. f!ecord the observed ficw on Data Sheet, OPS f orm 302-2, F?ow #4. 7.11.3.17 If Flow #4 is zero and the constant stall ~ flow observed in above steps is >_ 5 GPM, l then drive maintenance is indicated. 7.11.3.17.1 Mark the Drive Maintenance Indicated" line on Data Sheet, OPS Form 302-2. 7.11.3.17.2 Restore the CRD per Step 7.11.5 and then proceed with testing of other drives ae, required. 7.11.3.18 If Flow #4 is zero and constant flow from above steps is >3.5 but <5, further tests and data evaluation will be required to deters:ine if drive maintenance is indicated. i

J l OP 302 Page 23 Rev. 10 Date: 7/20/81 4 7.11.3.18.1 Mark the "Further Testing l Required" line on Data _ _.. - - ~ Sheet, OPS Form 302-2. - - ~ --- -- 7.11.3.18.2 Restore the CRD per Step 7.11.5 and proceed with testir g of other drives as ~ required. If Flow #4 is >0, a problem with the HCU 7.11.3.19 is indicated (leakage past directional control valve 121 or scram outlet valve 127; if the outlet scram valve were the caese, leakage would probably result in a high CRD probe temperature. Therefore, the more likely suspect is the insert directional control valve 121.). 7.11.3.19.1 To test the 121 valve, proceed as follows: 7.11.3.19.1.1 Close the exhaust water riser isolation valve 105. 7.11.3.19.1.2 Repeat the arithdraw stall flow test per Step 7.11.3.5, record the ~ observed flow on Data Sheet, OPS Fara 302-2, as Flow #5. 7.11.3.19.1.3 If Flow #5 is zero, then valve 121 is

OP 302 Page 24 Rev. 10 Date: 7/20/81 not closing properly and should be inspected. 10 ark the

• Wsive'121 3lppds 3nspectiDh

'iine on Data Sheet, DP5 forn 302-2. 7.11.3.19.1 A If Flow #5 is l >.2eto '(arther wing is Tequired. '9tark-the "Fitriher Required" line on Data Sheet, DPS Fem 302-2. 7.11.3.20 Restore the CRD per Step 7.11.5 and proceed with testing of other drives as required. 7.11.4 Insert Stall Flow Test - Dptional Test - Do only -if mquested to. 7.11.4.1 ihis 1=st does little to determine tte rendition of the drive, tut is useful in ~ Jeak testing valve 322. 7.11.4.2 To test the.122 valve, proceed as follows: 7.11.4.2.1 Select and insert to 00 the IRD associated with the HCU -to te tested. I m-

l 1 OP 302 Page 25 Rev. 10 Date: 7/20/81 7.11.4.2.2 Apply a continuous insert l signal to the drive and -- observe the drive water '--~ ~ --' flow. Record this fb on Data Sheet, DP5 Fora 202-2, as flow 46. /. 7.11.4.2.3 Ilose the exhaust water riser isolation valve 1D5. 7.11.4.2.4 App'ly a continuous insert signal to tiie drive and observe the drive water flow. Record this flow on Tata Sheet, DPS form 3D2-2, as flow f7. 7.11A.2.5 Compare flow 16 with Flow

1. 7.

7.11 A.2.5.1 TT Flowi6 = Vtw M,122 is mot leaking. 7.13.4.2.5.2 11 Flow 45 > Flow #7, then % 121 va'Ive -is not Posing pocperly wed quins % ction. 4tatt the "122 l Valve Heeds Tnspection" line on Tata Sheet, OPS Form 302-2. ( G G N @e

OP 302 Paga 26 Rev. 10 Date: 7/20/81 7.11.4.2.6 Open the exhaust water riser isolation valve IL. ___ ____ 7.11.5 ltestoration 7.11.5.1 Restore valves to operational alignment. 7.11.5,2 Reconnect electricc11y disconnected _ directional control valves. 7.'il.6 Attachments -~ 7.11.6.1 Data Sheet, OPS Fom 302-2 7.12 Control Rod Drive Accumulator Piston Seal Exercising 1. Reference 1.1 General Electric SIL No. 294. .Z. Sackground The-accumulator Tequires servicing when the seal around the piston allows excessive water to leak into the nitrogen system. The need for maintenance may be indicated by a high level alam which trips when suTficient water has ccTiected in we nitrogen rharging line. This water accumulation ran be due to nomal ~ ~ ~ ~' ~ ~~ ~~~ ~ leakage over a long period of time or the rapid leakage indicative of a seal problem. Eonsequently, the first action is to Temove the accumulated water and observe how long it takes the high level alam to reappear. If it is velati rely soon (less than ine week), s,eal wintenance is indicated. 3f seal 1naintenance is indicated, exercising the piston seal say rause it -in reseal, reduce l' akage and e mkelnaintenance unnecessary. The following. procedure fias .been.used.successfulJy to reseat the seal. (Refer to figure 7D.3) frocedure t l 7.12.1 Isolate the NCU by closing the isolation valves in l the following order: 101, 102, 113, 103, 104, 105, D 2. 7.12.2 Remove the water accumulation by closing valve 111 and opening P6 to drain the water. Slowly crack open ( valve 111 to blow out residual water and then close r

e O OP 302 Page 27 Rev. 10 Date: 7/20/81 111. Recharge with nitrogen if excessive' loss of mitrogen occurs in this maneuver and then I' lose PS. Reopen valve III. ~ ~ ~ ~ i 7.12.3 Slowly open valve 107 and drain to radwaste. This relieves the pressure on the top of the piston and moves -it to the top of the accumulator. ~7.12.4 tlose the lD7 valve and then open the 113 valve. ~ This repositions the accumulator' piston. 7.12.5 Close the 113 valve. Repeat steps 7.12.3 through 7.12.5 two times. 7.12.6 7.12.7 Slowly open the valves in the following order:

112, 713, ID2,101, 104,105, 103.

~ 7.12.6 to.3 the -date vhenthe Trocedure is rempleted. The of this procedure will te -indicated by -the ="eare period of time it takes the high level alarm to appear a_ gain. 31 the leaka.ge is not sufficiently teduced, proceed with the normal maintenance action _ yer the HCll Operation and Naintenance Manual. 7.13 tuntrol Rod Drive High Dperating Temperature Trouble Shooting. 7.13.1 Reference 7.13.1.1 Seneral _ Electric.SIL Wo.173. 1 7.13.2 Eackground 7.13.2.7 A number of operating EWR plants have questioned the basis for setting the Control itod Drive (CRD) high cooling water femperatune a'lars at >_50*F. The. purpose of l j -this SIL is to triefly tiistuss the Teasons i for this temperature n'larm setting to nutline the major ronditions which can tause er -indicate tigh CRD operating t temperature and to recommend corrective zctions when ti.gh IRD temperature is experienced or temperature alarms occur. ~/.13.3 Discussion (' I

OP 302 Page 28 Rev. 10 Date: 7/20/81 7.13.3.1 CR0 temperat.ures above 250*F can shorten y graphitar seal life and increase CRD drive i maintenaNe and CRD temperatures 350 F-550*F will result in a significant i reduction in strength of the graphitar seals. As a result of high IRD i temperatures, higher wear / breakage rates e can be anticipated when operating hot ~ drives. Quantitative definition of this rate of degradation is not available ~ because of the complexity of the factors involved relativu to CRD operating history shile bot. j Temperatures mver.350*F may also resu11 in q ~ a measurable delay in scram response times. 4 An increase to 400"F could result in up to J e v.nu monu aucTrase in Tne sur -insertien time for an otherwise ~ ~ ~ ~ - - ~~ ~~ ochnally performing CRD. However, this increase should not effect a normally performing CRD's ability to meet technical J specification limits. There are four l ammon causes for IRD high tooling water cooling water tempersture alams: L A leaking scram discharge valve. This is of concern as the CRD runs tot due is reactor water passing down through the drive and out the line to the k 3 stramliischarge volume, and wm runtinue to run totter as the scram discharge valve seat continues to erode. Eventually this could j interfere with normal drive mov; ment. 4 J low tooling water flow.

• 5

'e

e' OP 302 Paga 29 Rev. 10 Dnte: 7/20/81 CRD process diagrams specify a cooling water setting of reactor pressure + 12 . Psi to reactor pressure +25 psi. Low cooling water flow can be increased by adjustment of the cooling water I pressure regulator. A low pressure setting may cause one or more CRD's to alare on high temperature. 1 3. A defective Thermocouple circuit. 'In-this case the drive way not J mctually be running hot. Suspect circuits may be verified by following standard plant procedures. 4. A p' lugged cooling water orifice. Ibis will reduce flow to the individual drive and cause it to run .hnt. .A _uwria) f)),)Shinn forhninna (7.14) may assist in clearing the orifice. v " Recommended action of General Electric when high CRD temperature alams are received:" 1. Verify that other CRD aperating temperatures are normal. A los cooling water pressure regul~ator setting will nsult in higher than tiotsal CRD temperatures. Adjustment j nT the pressure regulator to increase flow should correct the problem. Check to detemine if the scram 2. discharge valve for the CRD in question is leaking. This will be indicated by un elevated temperature lit 41ydraulic Control Unit (HCU) valve 102. If the scram discharge valve is (

OP 302 Page 30 Rev. 10 D2te: 7/20/81 determined to be at fault, repair, adjust or replace in accordance with m the HCU Operation and Maintenance 1 Instruction Manual. (Submit M.R. for maintenance and management planning) 3. Siext Jdetermine if ibe thermocouple ) ricuit for the CRD is defective. (Submit M.R. for I&C dept. 1 investigation) 1 -4. If ' low too' ling water flow, a ' leaking scram discharge valve or a defective thermocouple circuit are not determined to be at fau'It, it may be presumed that the CRD cooling water - crifice is plugged. The flushing procedure presented in 7.14 is get=nondon for 12nshing -a ningged cooling water orifice. This procedure must be performed with the reactor in the cold shutdcwn condition. 1 5. Normal drive maintenance criteria rentinues to apply to "high temperature" CRDs (i.e., leakage rate, scram time, etc.). Be certain to -t.horoughly apply the criteria to CRDS d ich stabilize at temperatures above 350*F and schedule w-Stenance j appropriately. 4. Do not ettempt to cornet CRD -temperature alarms by applying i repeated drive signals. This will e 1m'h temporarily rool the Mrive with the effect of putting undesirable W erature cycles on the CRD. High temperature annunciators for a drive (

OP 302 Page 31 Rev. 10 Date:7/20/81 or drives may be acceptably patched-out providing the temperatures _.___ _____. - are checked on a resonable frequency such as once a week. 7.14 Mushin.g of CRD Hechanisms 7.14.1

Purpose:

-- [- The purpose of this procedure is to delineate a recommended step by step procedure for flushing rentaminats from both the drive mechanism rooling water orifice area and the associated Hydraulic I Control Unit (HCU) directional control valve block withdraw filter (c135) area. i 7.14.2 Initial Conditions: 7.14.2.1 The CRD to be flushed has been identified as having excessive drive temperatures during reactor operation and/or sluggish wnnurawat mon on. ms 7s inoicat.7ve m a plugged lha filter caused by particulates in the drive methanism drawn down into HCU following a scram and subsequent rod withdrawal. 7.44.2.2 The reactor shall be in the cold shutdown rendition. I 7.M.2.3 h Control Rod Drive ifydraulic System is 1 in cperation with nomal flows and I differential pressures established. i 7.M.3 W ocedure: W CAUTIONS 1. Dbserve proper HCU valving order when isolating or valving in HCU to prevent potential damage to CRD... \\ 2. Dbserve radiological precautions when flushing. Direct al'1 water to floor drains and note flush i cloths could be highly contaminated. k h e . e

OP 302 Prge 32 Rev. 10 Date: 7/20/81 7.14.3.1 Valve out HCU according to 7.10.1 and leave water side of accumulator vented through -~eccumulator valve 107. ~- 7.14.3.2 Commence static flush from both insert and 4 withdraw risers by connecting vent tubing 1 to vent valve blocks F101 and FlD2, j directing flow to floor drains for minimum of 45 minutes or until clean filter cloths result fif 21 sed). Reclose vent valves flD1 and FlD2. 1 7.14.3.3 Remove and inspect -filters 134 and 135, Wlacin.g if necessary using new 0-ring gackets. 7.14.3.4 Remove filter 135 and install a substitute P3 plug fabricated to accept a tygon tubing drain which is directed to the floor drains. ~ 7.14.3.5 Crack open insert riser isolation valve 101 and flush through P3 connection for approximately 5 minutes or until clean Tilter c'loths results (if used). 7.44.3.6 Mith valye 101 shut, crack open cooling water Tiser. isolation valve 104 and flush -through P3 rennection for.approximately 5 I ininutes. Of little or no flow 1s abserved, inspect cooling water check valve 738). ~7.14.3.7 Reinstall plug P3 with new filter 135 and D rins. gaskets. ~7.14.~3.B Return HCU to normal, verifying proper N 2 prechar.ge prior to opening c$arging water isolation valve 113. 7.14.3.9 Functionally check CRD operation by ] stroking and timing rod. If further CRD i venting and CRD speed adjustment does not

OP 302 Page 33 Rev. 10 Date: 7/20/71 cure sluggish operation, take oscilliscope traces to evaluate other problems. - - -... --.7.14. 3.10 Monitor drive temperatures upon return to hot operating condition. If drive rentinues to run hot a plugged tooling s i uater orifice within CRD wechanism1nay te ^' indicated. Once this is determined, the foreign material can normally ordy be i removed with the drive out of the reactor. l ~7.74.3.71 Removal of the ERD for maintenance should i be accomplished at the next planned maintenance outage. I 7.15. inadvertent Control Rod Withdrawal 7.15.1 Reference 7.15.1 General Electric SIL No. 292. 7.15.2

Background

-7.i5. 2.1 Several operating BWRs irave experienced malfunctions in the control rod drive . system that caused 2 control rod to continue to withdraw after the operator had terminated the rod withdraw rommand. The

purpose of this section is to discuss these occurrences and to present recommended i

. procedural guidelines for operator 1esponse. q 7.15.3 Discussion 7.15.3.7 Iv-idence indicates that the withdraw rontrol valve, No.122, failed to c~iose after the withdraw signal was terminated. %is failure could have resulted from -either en electrical or mechcnical j aalfunction causing the control rod to continue to drive aut. y 7.15.4 Procedural Guidelines (

i OP 302 Page 34 Rev. 10 Datei 7/20/81 7.15.4.1 Prior to planned insertion of fully withdrawn control rods during rod =-- 4xercising or sequence change insert the rod to position 44 then withdraw to position 46. Ifpon verification of proper 1 setting at position 45 the Tod may be ] withdrawn to 48. If the rod should fail to ~ -~~ settle et position 46 and continue to drive out to position 48 this indicates possible I failure of, valve No.122 and further i verification and corrective action may be necessary. 7.15.4.2 If an inadvertent control rod drive-out should occur during normal operation (i.e., the control rod continues to withdraw after the operator terminates the withdraw command), proceed as follows: ~ 1. If a timer malfunction alarm is observed, immediately initiate control rod insert by actuating the emergency insert switch. If a timer malfunction a'lars is not observed, use the normal i control rod insert switch to insert -the control rod. l 2. If the control rod drive does not respond, initiate a single contro'l rod I sm to insert the contro'1 rod. I '3. If the drive continues to demonstrate i occurrences of inadvertent withdrawal, the control rod should be inserted to position 00 q and the drive should be valved out of service mntil the fau!t is located and corrected. i 6

OP 302 Page 35 Rev. 10 Date: 7/20/81 7.16 Stuck CRD Collet 7.16.1 Procedure for Verifying a Ituck -- Collet - Ref. SIL 310 7.16.1.1 If a drifting control rnd is encountered, a stuck rollet ran be verified by driving to the full-in position and holding a ~ continuous insert signal until the ' isolation valves 101 and 102 can be closed. i M the 4 rive tiriits while isolated, the 1 rollet assembly is at fault. Reopen valves 1' 101 and 102. CAlffl0N: The operatin.g status uf1.he plant should be such that the drive q tould tirift full out without tausing a problem as there might be a delay in reopening valves. 7.16.E A +eing a stect Coli+t 7.16.2.1 If the reactor is at iin elevated pressure, an individual rod scrim may. free the r.oTlet. lf, as is me re likely, the drift is m. curing after a ncram {with the reactor at low or ambient pressure) the collet area may be flushed as follows: ~7.15.2.1.1 Drive out to position 48. 7.16.2.1.2 Elevate the CRD lirive Water Pressure to Reactor Pressure +450-500 psi. YA4.2dd -Give thewirive-cepeated continuous withdraw signals, i one or two minutes each. i 7.16.2.1.4 Fellowing 20 or 30 such witt1 draw signals, notch the ed back in to check collet <i l operation.

OP 302 Page 3E Rev. 10 Date: //20/81 1 7.16.2.1.5 Repeat if necessary until the CRD latches and .. unlatches reliably. . =..... _ _ _.,. "LAUTl0N" Enntrol Rod Drives with unlatched coTlets cannot be held at the inserted position without a CRD pump in Dperation. in the event that flushinD Waes mot torrect -the unlatched toTlet problem, ufer to Tech. Spec. 3.3.A.2 which requires "Iold Shutdown" within 4B iiours. i B. ALARMS AND MALFUNCTIDNS B.1 "CRD Accum Low Pressere/Hi Level" l 8.1.1 Panel 905, Section A-2, Window 2-4, CWD 579 B.l.2 2nitiatina Device: PS-130. 1D-129 B.1 A Automatic Action: 2nd Accumulator alam is Rod _g30cy.. S.1.5 Initial Dperator Action: 1. Dispatch PED to determine if low press or high level. ~ 2. llecharge accumulator or drain thru P6. B.1.E Subsequent Dperator Action: 1. Stone E.2 " Discharge Volume Hi Water level" E.2 'I Panel SD5, Section A-2, Window 7-4. EWD 555 E.2.2 2nitiatin_q Ilevice: LS 3D2-82A (B,C,D) B.2.'3 5etpoint: 39 gal. in the scram disch. volume. B.2A Automatic Action: lleactor Scram B.2.5 Initial Operator Action: 1. Iarry out Emergency Procedure #5D2. B.2.6 Subsequent Operator Action: 'l. Bypass disch volume high level scram signal with bypass switch on CRP 905. (

OP 302 Page 31 Rev. 10 Date: 7/20/81 1 1 I 8.3 "CRD Filter High Differential Pressure" 8.3.1 Panel 905, Section A-1, Window 9-2, CWD 498 " ~ " ' ' - ~ = ~ S.-3. 2 Discharge filter of CR0 Pp., PS 302-52

8.3.3 Setpoint

dp _ 20 PSID B.3.4 Automatic Action: Ncnc B.3.5 Initial Operator Action: 1. Shift filters. ~ ~ ~ ^ 4.33 Subsequent Operator Action: 1. Change and clean dirty filter. B.4 "IRD Pump A(B) low Suction Pressure" B.4.1 Location: Panel 905, Section A-1, Window 5-2 B.4.2 2nitiating Bevice: PS 3D2-51A(502-51B) BA.3 Setpoint: Sutt. press. 'IB" Hg Vac B.4.4 Automatic Action: None ..a.4.5 Initial Operator Action: 1. Check pressure and suction filter AP. 2. 'If abnormal-shift pumps and change filter. 3. If not abnormal, check valve line up and CST _.. _ _ _ _ _ level. B.5 "Chargin_a Water Low Pressure" A.5.1 Panel 905, Section 4-2, Window 8-2 E.5.2 Initiating Device: PT 306-55 B.5.3 Setpoint: 1400 psi.g B.3A Automatic Action: None B.3.3 ' Initial Dperator Action: 4testore Pressure 1. Eheck pump running. 2. Iheck system flow and TIV. 3. Iheck valve lineup. If a'larm from shifting pumps, then combined disch may hve to be 1.hrottled. Alarm may be from ar:munulators rhar. gin.g -(after a scram). B.5 3 Subsequent Dperator Action: 'i. Nene I m

OP 302 Page 38 Rev. 10 Date: 7/20/81 8.6 " Scram Pilot Air Header High/ Low Pressure"

8.6.1 Location

Panel 905, Section A-2, Window 2-2, _ -... _... = CWD 579 8.6.2 Initiating Device: 302-81 B.6.3 Setpoint: Air Header Press High 75 psi, Air H.eader Press Low 70 psi. / /. . 8. 6. 4 Automatic Action: None NOTE: If pressure gets low enough contov rod . scram valves wi11. start driflin.g open resulting in control rods going into the J tom. B.6.5 2nitial Dperator Action: L hiemine r.ause. ~.If entire inst. air. system pressure is low, start standby air compressor. B.6.6 Followup Action: 1. If rods have commenced to scram individually into ccrc, -ma=c11y cr.am -rcscler. 8.7 "CRD High Temperature" 6.7.1 Panel 905, Section A-1, Window 7-2, CWD 515 B.7.2 Initiating Device: Panel.921 Recorders 340-16A 12 LEE B.7.3 .Setpoint Temp mf 250"F vearted 1.7.4 Automatic Action: None B.'7.'i Israediate Dperator Action: (Refer to Appendix) '1. Identify ETO with high temp. 2. Check CRD cooling water flow. ~~ ~ 3. Do mot tool a hot CRD by giving it repeated ~ drive signals. After t.hecking for possible distharge scram valve' leakage, a CRD with a high 1.emperature alarm should te left-EUT. 4. Check valve lineup on CRD alarming.

OP 302 Page 39 Rev. 10 Date: 7/20/81 ~~ 8.7.6 Subsequent Operator Action: If temp still climbs after above, seals on CRD 1. may be lost and rod may be inoperable. 2. Refer to step 7.13. B.B "CRD Pump "A" (B) Bkr Tripped by Overload" Panel 905, Section A-1, Window 6-2, CWD 545 B.8.1 - B. B. 2 Initiating Device: Relay SlB

8.8.3 Setpoint

390 amps B.BA Automatic Actinn: Pnap Stops 1.E.3 ' Initial Operator Action: St5ft T10w tontro11er to manual and Teduce '). sulput to 40L 2. Stari3" [O pump. 'If TRD am="lators are charging wait until all are charged, then shift flow control to auto. After reason for trip is determined, shift back 3. .ic "t." (S) p=p re.:r.::fr.g after mitic.g at h=1 20 minutes for motor to cool. E.B.6 Subsequent Operator Action: If pump trips a second time, turn in NR to have 1. Maintenance rheck it out. .2. 11_=mmulators are chargins and/or sys. has been shutdown, pump discharge valve will have to %-throttled until system is up -in -full ,pnessune. B.9 " Discharge Volume Not Drained" E.B.'l Panel BDS, Section A-2, Window 9-2, CWD 579 B.S.2 ~1nitiating 1)evice: TS 302-B2F E.9.3 Setpoint: Accumulation of 3 ga'l. water in scram 1)ischarge Volume B.B.4 Automatic Action: Alarm only E.9.5 Initial Operator Action: i 1. If cause of alarm was not an occurrence of -a Reactor Scram, verify SDV vents and drains open. il i I e

OP 302 'Page 40 Rev. 10 Date: 7/20/81 l 8.9.6 Subsequent Operator Action: 1. Inspect the individual Control Rod Scram Valves _____ for evidence of leakage past the seat to the Scram Discharge Volume. S.10 "fRD A(B) High Filter D/P" 8.10.1 Panel 903, Section A-3, Window 8-8 (9-B), CWD 759 and 784 l 8.10.2 Initiating Device: Suction Filter Barton Gauge DP 1302-100A (DP 1302-1008) 4 B.lD.3 Setpoint: Tilter 1)/P __13 P5ID ~ 4.10A Automatic Action: Alare only KlD.5 Jnitia').Dperator Action: '). 1)ispatch operator -to verify ti_qh ti/p rondition. 2. Shift to standby CRD pump. 8.10.6 Subsequent Operator Action: l 1. Change filter ele:nents and restore filter to norma') standhv conditinn. i B.11 " Rod Drift" ~-- .B.11.1 Panel 905, Section~ A-2, Windcw 4-1, CWD 526 '~~~~ -- -- 8.lL2 Initiating Device: Relay 134A (B,C,D) B. l').3 5etpoint: Rod moving from even numbered position that is not se'lected and bein_q driven. B.ll.4 Automatic Action: Hone B.'ll.5 Imediate Action: '). 3e' lect ' Drifting llod and return it to desined position. A.11.6 . Subsequent Operator Action: 1. Investigate cause. 2. Eheck for excessive tooling water flow. f 3. Refer to 7.'15 and '7.76. i S.12 " Rod O w rtravel" B.'12.1 Panel 905, Section A-2, Window 6-1, CWD 526 (719E 534 SH. 5) 8.12.2 Initiating Device: Relay 136 (

OP 302 Page 41 Rev. 10 Date: 7/20/81 8.12.3 Setpoint: Control Rod withdrawal beyond indicated position 48. -S.12.4 Automatic Action: None 8.12.5 Initial Operator Action: 1. Insert Control Rod to attempt to recouple the ltod and to perfo'nn a coupling check. " " 8.12.6 Subsequent Operator Action: 1. If Rod cannot be coupled, insert Rod fully to position ".00" and electrically siisarm it. B.13 ERD Fails to Unlatch 1333 1.ocation: Hone B.13.2 Initiating Devire: Hone B.13.3 Setpoint: None 8.13.4 Automatic Action: None B.13.5 Initial Operator Action: (Refer to Appendix) 1. Hay be caused by excessive air trapped in i.,d.Lui4tinipiis. Water sMuld -fkst try pulsing drive with insert signals to flush the air out. If this fails, vent insert withdraw lines from local high point vent valves. 2. May.be caused by pluggin.g of small filters mushar 134, ~35 or 136 located in hydraulic rentrol unit control valve cluster. These are -easily removed for cleaning. 3. failure to unlatch in the withdraw direction may be caused by a leaking scram inlet valve. Note h pressure -test points P1, P2, P3 and T4 inay be used for trouble shooting a troub'lesom drive. kk.14 "CRD Drifting In" .B.14.1 location: None B.14.2 Initiating Device: None B.14.3 5etpoint: Wone B.14.4 Automatic Action: None hew ,?

OP 302 Page 42 Rev. 10 Date: 7/20/81 8.14.5 ' Initial Operator Action: 1 1. Check for excessive cooling water pressure. i This could occur if cooling water pressure reached approximately 70 psig above reactor pressure. 2. Check for leaking scram inlet valve. B.15 Low Drive Water and/or Cooling Water Pressure 6.15.1 tocation: None B.15.2 initiating Device: None B.15.3 Setpoint: Hone 4.15A Automatic Action: None JL 35.5 . Initial Sperator Action: 7. Soma ~ny way be tontrolled with pmssure rentrol ~ valves. 2 Check for failure of flow control valve or controller. 3. Switrh tn manua3 rnntt~ni nr aitornat.o fiaw tontml system. - ~ - - - - 4-- Check for low instrument air pressure in 30 psig ~ ~~ ~ ~ ~ ~ ~ air supply to flow control station. B.15

• Rod I) rop" B.15.7 Indications to Dperator:

1. Sudden unexpected and otherwise unaccountable incmase in neutron flux on Panel 905. Rapid step thange in neutron flux monitoring recorder traces on Panel 905. 2. Change in major plant parameters as a result of the msulting power excursion as indicated by a vessel level -transient, vessel pressure -increase, feedwater flow increase, steam flow increase as indicated on Panel 905, or electrical output increase at the Computer Select Console in the Control Room. I 3. LPRM's or IRM's in the vicinity of the dropped rod initiating in high flux alarms. (

OP 302 Page 43 Rev. 10 Date: 7/20/81 4. Rod position indicator gives evidence of rod motion. 5. Possible reactor scram. 6. With local fuel damage or melting, possible steam line, off gas, and stack gas radiation alarms on Panel 904. '7. With plant at less than 10% power, -the Rod Worth Minimizer will indicate a rod out of sequence. A 1B.2 Setpoint: ERD system faiJure resulting in a rad drap. 6.16.3 Automatic Action: eiOTE: The following automatic actions am based on worst case conditions. The efegree of the transient will vary widely depending on initial conditions and proper system functioning. 4. J.cactor -scr4= 4t 4M 4cvel of 45 Jull 4 calc, er APRM flow biased scram. 2. With a si_gnificant fission product release, the Tollowing will occur: A steam line high radiation O times nonnal Tull power. background level) will scram the reactor, close the main steam isolation valves, trip the mechanical vacuum pump and close the vacuum pump suction valve. B.15.4 Immediate Operator Action: L If a Reactor Scram occuts, carry nut the actions of Emergency Procedure 502, Emergency Shutdown. 2. If the rod drop tsas not resulted in a Reactor Scram, select and drive the affected rod to the fully inserted positien and electrically disarm its associated directional control valves. B.36.5 Subsequent Action: ( 1 i

i OP 302 Page 44 Rev. 10 Date: 7/20/81 h 1. Maintain constant surveillance of primary coolant activity to aid in the evaluation of the - extent of possible fuel damage. l 2. If a Reactor Scram has resulted, continue shutdown in accordance with Emergency Precedure 502, Emergency Shutdown. 3. If necessary, monitor for background radiation = - - - to verify a high steam line radiation condition. -4. Notify the Unit Superintendent or his designee, j i who wTl'1 provide instructions for further actions. a.17 " Abnormal Control Rod Motion" 2.'17.1 2ndications to Dperrtor: 1. " Rod Drift" alam on Panel 905 in the Iontrol Room. 2. Rod position indicator gives evidence of rod-Ark:c4 rift-in 1:1.1:uing,.::n 23:crt sig=1. 3. Rod position indicator gives evidence of rod-titive drift-out following a withdraw signal. i 4. Rod position indicator gives evidence of rod motion with no notion intended. 5. Indication of a single rod scram. 5. 1PRM high alarm, possible APRM high flux, meutron monitoring system trip, 7tod Block, litM iii.ph, or Reactor Channel A(B) Scram on' Panel 905. 7. Unaccountable thange in local neutron flux and major. plant parameters such as reactor pressure, teactor level, feedwater flow, steam flow, generator output as a result of the reactivity chan_ge. 8.17.2 Setpoint: CRD system failure resulting in control Tod notion in the wrong direction, control -rod notion when it is not intended or N

OP 302 Pege 45 Rev. 10 Date: 7/20/81 I motion of a nonselected rod. 8.17.3 Automatic Action: --- NOTE: Abnormal motion may be such that no trip occurs or that a power reduction occurs. 4 1. Iteactor Scram (IRM or APRM trip) on Rod - withdrawal. /-/ - 2. IRM or APRM rod block on local high flux 4 conditions. B.17.4 1 mediate Dperator Action: 'l. If unintended rod withdrawal is indicated, Tttempt to stop 1.he 1 notion with an -insert Si_gnal. If rod motion continues, scram the rod from Iontro'l 1toom Panel 915. { 2. 3f unintended rod insertion is indicated, allow the rod to insert until motion stops or the "00" position is reached. 2. Rcd;;cc noctor cccircchtion -th L -raintain Yated30werat1ess1.han 2011WT. To not l-exceed Rx Power /Recirt. Flow limitations. 4. .11 a rod drift alarm occurs, immediately select the drifting rod (the rod status display has a " Drift" light for each individual rod) and pulse it with an insert signal. This should correct 1.he drift and allow the CRD to settle into an even-numbered position. 5. If a malfunction has resulted in an individual rontrol rod scram, dispatch an vperator to the IRD hydraulir area to survey for str.uctural or piping failure. 6. If the CRD double notches during single-notch movement, if notch movement is slow or erratic, at the CRD fails to settle or settles slowly, discontinue further rod movement, check for womal supply flow, drive water pressure, and coolin.g water pressure and adjust as necessary.

OP 302 Pagm 46 Rev. 10 Date: 7/20/81 i 8.17.5 Subsequent Operator Action: 1 1. If a control rod is determined to be stuck, proceed as follows: _.. _ _.. _... ~. _. a. Disarm the rod electrically in accordance with Operating Procedure 302. b. Notify the Unit Superintendent or his designee for instructions for further action. 2. If the CRD double-notches during sin _gle notch 1novement, investigate the following: Excessive drive header pressure; adjust e. sith. drive pressure control switch on Pane) 905 and rheck for proper supply flow, pressure and stabilizing valve operation. 6. Air in hydraulic control lines, vent in accordance with Operating Procedure 302. 1 thary Snr nnema, enni ; nn un tn e haaAar nroce,.ne -{epproximately 33 psi sbove reactor pressure). if ixcessive, adjust the cooling water pressure- ~ ~ ~ ~ ~ ~ ~ ~ ~ control switch on Panel 905 to obtain the proper pressure. If the system Ifoes not respond, dispatch an operator to the pressure rentrol station to take local-1nanual rentrol. 4. If the above corrective action is unsuccessful, notify the Unit Superintendent or his designee for instructions for Turther action. B.lB % ss of Rod Control" B.lfLl Indications to Operator: 1. Rod-sciect pushbutton does not illuminate when tiepressed. l 2. An individual selected control rod can be inserted but not withdrawn. i 3. tio movement indication (based on in core flux monitors and rod position indicators) for an individual selected control rod. ~

4 OP 302 Page 47 Rev. 10 Date: 7 /20/ 81 4. " Rod-out Permissive", " Rod Out", or " Rod In" lights do not illuminate during attempted rod. movement. 5. One or more of the following annunciated alarms on Panel 905 in the Control Room. (a) " Rod Out Block" with associated rod block display illuminated. (b) "CRD Water Pump A(B) Low Suction Pressure". (c) "fRD Water Pump A(B) Breaker Tripped by Dver'icad". (d) " Charging Water Low Pressure". . le.) "LRD Filter High DP" ~ (f) " Scram Pilot Air Header High/ Low Pressure". B.lB.2 Setpoint: CRD System failure resulting in a loss of a control rod. B.18.3 Automatic Action: 1 Thn PD". nnmn will trin nn inw custinn raro c cura flB"41g Abs) and pump overload {-390-amps). ~ 6.11.~4 ~~Immelfiate Operator Action: ~ 1. If loss of rod control results from a rod black, check the Rod Block Display to detemine its rause and follow the corrective action 18e'lineated in the Alam Book. 2. Attempt to move the rod with increased drive pressure by adjusting the Drive Pressure Valve at Panel 905 in the Control Room. Do not exceed a ymssure of 390 psi above reactor pressure. 3. lf a loss of power to the rod control circuits is indicated, check the " Rod Select Power" switch located on Panel 905 on the "On" position. 4. If a low or loss of pressure in the hydraulic system supply header is indicated, take the following action: I -.~..

l i OP 302 Page 48 Rev. 10 Date: 7/2 0/81 If the operating CR0 pump has tripped off a. on loss of power, low suction or overload, start the standby pump and verify normal I system operation. 1 b. If mither CR0 pump can be started,, detraese power by reducing recirculation flow to a minimum and manually scram the reactor. x. Trip of the standby pump on low suction pressure would indicate a low level /or high 1.emperature in the condensate storage tank -eraplugged supply filter. ~ NOTE: If a low pressure is accompanied by a supply filter high differential pressure, dispatch an operator to open the filter byp:.cc antil.the ethcr me p :.en te placed in service mr the filter is changed. 21. At %e ' flow control station, verify a proper flow of 75 spm. If the flow is abnonnal, dispatch an operator to check for low instrument air pressure in the 30 psig air supply. Attempt to re-establish proper flow with the flow controller while u nitoring drive header pressure and drive Inoling header pressure. 'If #e flow rentrol valve fails to respond, dispatch an operator to isolate it and place the standby unit in service. e. I)ispatch an operator to check the system l 1 for possible leakage, especially at accumulator drain valves. 1 1 h

OP 302 Page 49 Rev. 10 Date: 7 /20/81 5. If a drive fails to unlatch and withdraw (or if withdrawal is interrupted by possible collet .-- locking), proceed as follows: a. Cause may be excessive air trapped in the hydraulic piping. Attempt to flush the i drive by using two tonsecutive insert signals. b. Check for no mal (approximately 30 psi above reactor pressure) cooling water p mssure. 'If excessive, adjust the roo' ling water pressure control valve to obtain the proper pressure. If the roo' ling water pmssure contro'l vilve fails -10 respond, isolate it and place the manual pressure control valve in service. 6. If loss of rod control occurs after a scram, et*tt tigit Tiii m om vaive= have closed after _ _ _ _ _ _ _ _ reset by noting that the red " Scram" display above the selected rod's position is not illuminated. B.lB.'S Subsequent Dperator Action: 1. 3f a control rod is determined to be inoperable, proceed as Tollrus: a. Any control rod which fails to move after all attempts to correct the malf5nction have failed should be treated as an inoperable 1 rod and disarmed electrical'ly in accordance with Dperating Procedure 302. its final position of the rod wit 1 depend on the conditions of the failure, b. Notify the Unit Superintendent or his . designee for further instructions. 2. Check.that the isolation shutoff valves in the in'draulic lines serving the drive in question l I are fu11 cpen. g

o OP 302 Page 50 Rev. 10 Date: 7/20/01 3. If low instrument air supply pressure is indicated, check the air filter for possible Clean filters as clogging with foreign matter. ^" ~ necessary. If low pressure was due to supply filter high 4. Jifferential pressure, have the filter cieaned j or replaced and returned to service. 8.19 " Rod-to-Drive Coupling Failure" B.19.1 Indications to Operator: " Rod Dvertravel" alam en Panel 3D5 with Tod 1. psition display of Amcoupled rod going 11 ark xiuring a coupling check. Changing rod position indication with no local 2. flux response. 8.19.2 Setpoint: Coupling failure resulting in tne separation of a coi..rol rod from its associated drive. 4 1S.3 AutomaticJktion: - None ~- 1.79.4 ~3mmediate~Dperator Action: 1. 3f a " Rod Dvertravel" alarm occurs while the Teactor is critical, attempt to establish the position of the tontrol rod using the nuclear instruments on Panel 905 in the Control Room. If it can be definitely established that the 2. control roc' is fully withdrawn, insert the drive iwo or three notches and then withdraw it to the full-2 rat position. Hold the rod switch an ' Rod-Dut-Notch and the notch-override switch on " Notch-Override" and observe that 1.he rod position display inaintains a readout of "4B" with radiacklighting r.nd the " Rod Dvertravel" alarm remains silent. If there is an indication that the control rod 3. is not fully withdrawn, insert the CRD one notch at a 1.ime until a local flu response is

OP 302 Pag 2 51 Rev. 10 Date: 7/20/81 observable or the mechanitm is stopped by the cantrol rod. b.19.5 Subsequent Operator Action: 1. If the CRD is fully withdrawn and cannot be coupled after several atterpts, fully insert and electrically disarm the CRD in accordance with Dperating Procedure 302. 2. If the control rod was not fully withdrawn and upon inserting the CRD, a local flux response indicated that the control rod and ERD were in contact, apply a withdraw signal to detemine if the rod and drive have successfully coupled. If the CRD cannot be coupled after three attempts, electrically disarm the CRD in accordance with Operating Procedure 302. ~3. If the control rod was not fully withdrawn and cannot be inserted by CRD movement, notify the -Uhit Superintendent or-his designee-for4urther ~-~ ~~ instructions. B 20 " Scram. System Fai1are" B.20.1 Indications to Dperator: L The following will indicate the reduction or loss of ability to initiate a full emergency scram: "CRD Accumulator Low Pres /Hi_gh Level" alam a. Panel 965 and resultant " Rod Block" alam. t.

• Disctrarge Volume Not Brained" alam (3 ga'llons) Panel S05.

" Discharge Volume High Level" alam (19 r ga'llons) on Panel 905 and resuItant Rod j Riock" alam. d. "Distharge Volume Hi.gh Water Leve'1" alaru (39 gaIlons) and resultant reactor scram alam Panel 905. e a

O CP 302 Page 52 Fev. 10 Date: 7/20/81 2. The following will indicate that a full scram has failed to initiate: a. Scram display above rod position display does not illuminate or position indication does not change after a scram indicating e CPD has failed to respond to a scraio signal. b. Position indicator reveals a dontrol rod (s) has not fully inserted fo110 win.q a reactor scram. f.20.2 Setpoint: Scram system failure restitisig in the -. reduction -or ioss of abiJity 2D initiate a full emergency scram or failure of a scram to be completed. 6.20.3 Automatic Action: 1. Reactor will scram on a discharge volume high water level (39 gallons). 2. -CRD h.uusulator -inw pi essure vr t.igh level alarm, or a discharge volume high level alarm erill initiate rod blocks. NOTE: If accumulator pressure drops below reactor pressure, the insert port .: ball-check valve will shift allowing wattor water to provide full-scram ~ capability. E.20.4 Immediate Operator Action: L If a rentrol tod(s) fails to Tu'lly insert following a reactor scram, selett the affected Tod(s) and insert to the *00" position. Hake a notation in the Control Rod Surveillance Log. 2. If a "CRD Accumulator low Pressure and/or Hi_gh level" alarm occurs, dispatch an operator to check the accumulator monitor racks to determine the affected accumulator. .a e

OP 302 Pag 2 53 R:v. 10 Date: 7/20/81 3. If a " Discharge Volume Not Drained" or " Discharge Volume High Level" alarm occurs, __ check the position (open during normal reactor operation) of the discharge volume drain and vent valves by noting the indicating lamps on Panel S05. Check the "Dischar_ge Volume Isolation Test" switch in " Normal". 8.20.5 Subsequent Operator Action: 1. 11 an individual control rod has failed to Tespond to a scram signal, investigate possibility that one or both scram valves have failed to open. 2. If an accumulator low pressure condition is indicated, check for leaks at the hydraulic control unit, especially the gas charging connection. Recharge the accumulator as necessary in accordance with Operating Procedure 302. ~ ~ ~ 3.- If an accumislator water leak is ' indicated,The ~ ~~ ~ ~ ~ alarm could have been initiated by water leaking by an accumulator piston. Proceed as follows: a. Elose valve 111 on accumulator instrumentation b' lock. A Slowly loosen and then remove the cap at connection 76. z Larefully reopen vulve 111 to blow out noisture, then close va'Ive llL id. 4teplace rap at P6 and then reopen valve j TI'l. 4. Notify the Unit Superintendent or his designee for instructions for further action. 9. EHECKOFF LISTS 9.1 SPS Form 302-1, t'alve Checkoff List ,( 3.2 EPS Form 302-2

OP 302 Page 54 Rev. 10 Dato: 7/20/81 10. FIGURtS 10.1 Accumulator Precharge Nitrogen Pr ssure Versus . -- --- -- -- - -- - Ambient Temperature 10.2 CRD HCU Accumulator Piston Seal Maintenance Checkout Procedure. i JN:ws 9 A J I O j 4 ^- -~~ = = -..-=.-- -- 4 e e d 1 1i l l

OP 302 Page 55 Rev. 10 Date: 7 /2 0/81 \\ APPENDIX 1 Control Rod Collet Retainer Tube Cracking Duritig n inspection of a disassembled control rod ddve (CRD) at'a domestic GE BWR, cracking of a collet retainer tube (referred to as the 1048 1967P2) collet housing in the CRD maintenance manual, GE part number was observed. The cracking noted to date has been found to begin on the outer surface of the rollet retainer tube approximately six inches tiown the tube. Seneral Electric has attributed this cracking to thermal cycles during hot scram, followed by exposure to crygenated CRD cooling water which can be aggressive to sensitized materials. In CRD's examined thus far, the cracking is generally shallow and confined to the area where the tube This tube ha a very low mechanical loading anc'. wall changes thickness. However. should the probability of complete failure is extremely remote. The cracking progress to a point of complete circumferential separation the IRD would be rendered inoperable. 7he followingTaeneralTlectric recomendations shall be implemented: If a CRD fails to respond to the nomal insert romand (reartnr 1. pressure plus 250 to 300 psi). Install the dp instrumentation and verify that hydraulic a. pressures am being applied to the IRD Ifrive piston. 1. 31the ERD will not insert with normal system drive pressure mnder the piston, it should be 2fe:lared inoperable and no further attempt should be made to move the Tirive unless authorized by the Unit Superintendent. Such a CRD should be I electrically disarmed and hydraulically isolated to preclude Scramming the possibility of inadvertently scramming the CRD. a CRD having a' separated collet retainer tube would result in ~ 4i unnecessary damage to the drive. N 1

~ OP 302 Page 56 'l Rev. 10 Date: 7/20/81 j APPENDIX 1_ To reduce the severity of thermal cycles imposed on the CRD the temperature should be allowed to stabilize for about three minute 1. fellowing its withdrawal for a hot test scram. After 1)o not cool a hot CRD by giving it repeated drive signals. i checking for possible discharge scram valve leakage, a CRD w th a 3. Schedule such a CRD for high tecperature alarm should be left HDT. M utenance during the next refueh ng outage. for.further details an the control. rod rollet retainer tube tracking refer'to GE SIL 139 of 7/25/75. e -_ 6_ M e oO e t =

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p._ ( l' $2 195 th._ draw _ g t. 8 m I PROCEDUREm 5, Drive ->t "N' !!cter Suoply 103 MP 1. Ito etd H00 - c1cse valves ih fo11cwing ceder: Intert .!0) i, 1 1, 102 113, 103, 104, 105, 112. x Remdve accumulat'ed v ater by cicsing 111, cpcr.ir ,a y 2. _,cfM. yp * [,<,-O Pd and crec':ing 111 cpen to bica cut resid:c'. g y-Wdter. Rocharge with nitregon if needed cad g 1 dave P6 closed and 111 cpen. Drain-ront 105 112 3, slcwly 6 pen 107 and drain to cican rad.raste. T Coolind to dxhaunt To scr'ani t ves the p ston to the top of the cccu lateg 2 Frc 113 llator Wdtef - dischat'sle .g dharsing - h h hdador heeder ., 4. Closh 167 and cpcn 113 - this re.cositions the pit,tod. g. ,da t.? r i / 5. Clos 6 113. n 70 I g L l 5. Repedt stopi 3 through 5 two t' three tiras. o N k "2 7. Slowly opon the valves id the following crder: g 112,113,102,101,104,10$,103. N thaecingJ t ~ iii syste j 8. L g the date v. ten this procedure is cc: picted. If the 1cVt. alarm reappears soon, p ston CL5) CP5 k,, s, N j seal m81ntchance is apprcpriate.. g sg .. m 14 A.Q I -o i N o \\- %3 n n tilD HCU ACdVNULATOR c. F" Pl$tdMSEALMA!NTENANdECHECK0UTPROCECURE s i ---.-m 4m ""}}