ML17251A478
| ML17251A478 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/18/1988 |
| From: | Specter S ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17251A473 | List: |
| References | |
| PT-7, NUDOCS 8905160088 | |
| Download: ML17251A478 (36) | |
Text
ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER PROCEDURE NO.
REV.
NO.
HYDRO TEST 0 C OR COO NT CHN CAL EVIEW PORC REVIEW DATE PLANT SUPER TENDENT QA~
NON-QA REVIEWED BY:
EFFECTIVE DATE CATEGORY 1.0 GONNA STATlot" SyART:
OATH.
THIS PROCEDURE CONTAINS 14 PAGES ylhhE GPMPLET~D TIME:
8905i60088 890503 PDR ADOCK 05000240 P
PDC lk Vj
I
PT-7: 1 1.0 1.2 HHRQSjj'o verify leak tightness following maintenance and modification and to hydrostatically test the Reactor Coolant system.
To perform VT-2, visual leakage inspection of the Reactor Coolant System as per reference 3.3.
2.0 TEST RE UIREMENTS:
2.1 2 '
Following
- opening, modification and repair of the Reactor Coolant
- System, qualified test personnel shall maintain a pressure of 2235 psig for 10 minutes and as long as qualified inspection personnel require to verify leak tightness of the items specified in attached Check List gl.
Prior to the end of each ISI inspection interval (12-31-79, 12-31-89, 12-31-99, 12-31-09) qualified test personnel shall maintain a
Reactor Coolant System pressure in accordance with paragraph IHB-5222 of Reference 3.3 and temperature in accordance with Figure 3.1-1, Section 3.1 of Reference 3.4 for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and as long as qualified inspection personnel require to verify leak tightness of the items specified in attached Check List g2.
(340 at 2352 psig is acceptable for current Technical Specification revision).
3.0 REFERENCES
3.1 3.2 3.3 3.4 3.5 QA Manual, Appendix B.
Reactor Coolant System Flow Diagram in Q.A. Manual, Appendix A..
A.S.M.E.,Section XI.
Technical Specifications.
Environmental Equipment Qualifications Form EEQ-1 Package No.
3A (located in Maintenance Office)
Reactor Head Vent Solenoid Valves 590,
- 591, 592
& 593.
I.$
0 Jq F 't 4
PT-7: 2 4.0 LCODN 4 '
Residual Heat Removal Loop is in service to control residual core heat or isolated per O-l.l.
4 ~ 1.1 Overpressure protection system in service whenever RHR system is in operation.
4 '
Operating Procedure O-l.l is done up to step 5.31 or N/A if crevise cleaning in progress.
4.F 1 Operating Procedure 0-10 is done up to step 5.30 or N/A if procedures O-l.l is being used.
4.3 Prigary system temperature is
> test temperature of 340 F.
4 '
The following systems and/or equipment are available for service:
4'.1 4 '
Excess letdown.
Block valves for pressurizer power operated relief valves (MOV-515 and MOV-516).
4.4 '
Sufficient personnel are available to completely check, tighten, and/or repair all areas of probable leakage.
4.4.4 Steam Generators'A" and "B" are filled to normal operating level and secondary system is intact and ready to receive steam up to the closed Main Steam Isolation valves.
4'.5 One atmospheric power relief valve is operable.
4 '
All vent hoses have been disconnected from system component vents and blank flanges reinstalled.
4 ~ 5 Quality Control has been notified to assign qualified inspector arg provide list of maintenance items for check list.
J<,
'I
PT-7: 3
~O
~
If any change occurs in the normal operation of the 4 head vent valves
- 4590, 591,
- 592, or 593 such as increased seat leakage or stroke time, initiate a
Maintenance Work Request.
4 '
A Health Physics Work Permit has been obtained.
Any areas not normally entered (e.g. - Sump A) should be surveyed prior to entry.
5 ~ 0 PRECAUTIONS:
5.1 5.2 5.3 5.4 5.5 5 '
5 '
To protect NIS detectors a Reactor Compartment fan cooler muat be in service when temperature in RCS is above 135 A rod control shroud fan must be in operation when RCS temperature is greater than 135 F.
The Safety Injection signal from secondary side (Low steam
- Pressure,
< 514 psig) must be defeated, during
- hydro, whenever RCS pressure is in excess of 1992 psig (automatic unblock of S.I.).
The over pressure protection system shall be in operation whenever RHR is in service.
The Residual Heat Removal System must be isolated from the Reactor Coolant System before increasing system pressure above 450 psig.
Both pressurizer PORVs must be operable with a lift setting of 410 psig (435 psig. T.S.)
and aligned per 0-7 whenever the temperature of one or more of the RCS cold legs is 350 F
(330 F T.S.),
or the residual heat removal system is in operation, except one PORV may be inoperable for seven days.
If these conditions cannot be met, the Primary System must be depressurized and vented through a
> 1.1 square inch vent(s) within next 8
hours.
Maintain RCS in a
vented condition until both PORVs have been.restored to operable status.
Venting of system is accomplished by using step 5.39 of 0-2.2.
0 Reactor coolant temperature must be less than 350 F
before Residual Heat Removal System is returned to service.
4
PT-7: 4 5.8 5 '
When the RHR system is in operation, and the RCS temperature is greater than 200 F, a
maximum of 2
charging pumps are to be operated
$o prevent over-pressuring the RHR system.
Below 200 F, the operation of 3 charging pumps is allowable but should be avoided if possible.
If RHR system Hx begins to flash, it may be necessary to further open MOV-738A and MOV-738B to cool them below flash temperature.
6.0 INSTRUCT 0 S:
6.1 6 ~ 1.1 Perform the following to simulate normal operating pressure for 2
of 3
pressure channels per steam generator:
Place ~ot steam header Atmospheric Relief Valves in 6 '
Direct I&C to simulate normal operating steam generator pressure for 2
of 3
pressure channels per steam generators (700 to 900 psig).
6.1.3 Place both steam header Atmospheric Relief Valves in Auto, if desired.
(N/A step if not desired).
6.2 Stop one of the two operating Reactor Coolant Pumps.
6 '
- 6. 3.'
6
~ 3.2 6'.3 Place excess letdown system in service per following steps:
Open Component Cooling Water to excess letdown HX.
AOV-745 Open Open AOV-310 (Excess Letdown Stop Valve).
Place AOV-312 (Excess Letdown Diversion Valve) to normal.
6'.4 Control Reactor Coolant System Pressure with HCV-123 (Excess Letdown Plow Control Valve) and/or charging pump
- speed, closely watching that primary system pressure is being controlled at about 350 psig as read on PR-420.
'L gt I 'I
~I I
0 1
6 '
6.5 6.6 6 ~ 6.1 6 ~ 6 ~ 2 6.6.3 6 '
6.7 Close or verify closed, RHR letdown valve HCV-133.
HCV-133 Closed Close normal letdown oriiices isolation valves.
200A Closed 200B Closed 202 Closed With removal of Residual
- Heat, Removal Loop from service, the primary system cooling capability will be reduced to that of heat removal via the S/G.
If more cooling is
- required, primary system temperatures may be controlled by steam release from S.G.'s to the atmosphere.
Stop RHR pump(s) if operating.
A RHR Pump B RHR Pump Close or verify closed, RHR Isolation Valves:
MOV 700 Closed MOV 701 Closed MOV 720 Closed MOV 721 Closed Throttle MOV-738A and MOV-738B Component Cooling Water to the "A" and "B" RHRS HX.
CAUTION:
MOV-738A Throttled MOV-738B Throttled If RHRS HX begins to flash, it may be necessary to further open MOV-738A and MOV-738B to cool them below flash temperature.
6.7.1 Close or verify closed, HCV 624 and HCV 625.
y
?~
4 0
PT-7: 6 6.8 6'.1 6 ~ 9 6 ~ 9 ~ 1 When RCS temperature
> 340 F and after RHR system removed from service, the reactor vessel overpressure protection system is to be taken out of service before pressure increases above 350 psig.
RCS ) 340oF RHR System out of service.
To remove reactor vessel overpressure protection
- system, perform the following steps:
Block relief valve PC-430 actuation by SOV-8619A switch to the block position.
6 '
Block relief valve PC-431 actuation by SOV-8619B switch to the block position.
6'.3 Place Surge Tank V-802A charge valve SOV-8616A switch to the closed position.
6'.4 6'.5 Place Surge Tank V-802B charge valve SOV-8616B switch to the closed position.
Place PORV switches in Auto Position.
PCV-431C Auto PCV-430 Auto 6 '
6'.7 6 ~ 10 Open MOV 516 {Block valve for PCV 430).
Open Open MOV-515 {Block valve for PCV-431C).
Open Verify DC power available to the Reactor Head Vent solenoid valves, green lites on, valves closed.
NOTE If any change occurs in the normal operation of the 4 head vent valves
$590,
- 591, 592, or 593 such as increased seat leakage or stroke time, initiate a
Maintenance cwork Request.
6 ~ 10
~ 1 6'0 '
SOV 590
& 592 SOV 591
& 593
IE 0
PT-7: 7 Open the two (2) lower Reactor Head Vent solenoid valves.
SOV-592 open SOV-593 open Xf Hydro is terminated before all pressure plateaus have been
- reached, N/A steps not performed on procedure and data sheet.
Continue with Step 6.14.
Ensure set point of HCV 431K is at 2235 and auto mode.
If for 10 year test, set to 2350 and auto mode.
Auto 2235 2350 CAUTION:
Avoid rapid rate of change in pressure or set point to prevent operation of the power operated relief valves.
Indicate which Check Sheet will be completed and indicate the final pressure in Step 6.13.4.
Check Sheet 4
CAUTION:
Raise pressure slowly to avoid opening PCV 430 and PCV 431C.
The following are desired pressure plateaus during Hydro:
Begin system pressure increase starting at. 325 psig by adjusting excess letdown controller HCV-123 and/or charging pump
- speed, stopping long enough at each pressure level for a
complete inspection of the components under pressure.
When. making a visual inspection of reactor coolant
- system, specifically cover the areas as per attached check sheets.
These are areas which are more susceptible to leakage as well as areas which must be verified for integrity to conform to Technical Specification requirements.
Areas listed on Check Sheet 1 are to be checked to meet Step
- 2. 1.
Areas listed in Check Sheet 2 need only be verified to meet Step 2 ~ 2 ~
P x
$ 1 l
10
PT-7: 8 325 psig plateau reached and inspection completed.
Switch off PI-420 before 700 psig.
CAUTION:
Do not exceed 1600 psig unless the S.I. accumulators are aligned for operation.
when RCS pressure is at 1500 psig align S.I. accumulators for service as follows:
S.I. accumulator Boron Concentration
>1800 PPM.
>>A<< Accumulator
>>B<< Accumulator S.I. accumulator pressure
>700 psig.
>>A>> Accumulator
>>B>> Accumulator S.I. accumulator levels 50 - 824.
>>A<< Accumulator
>>B>> Accumulator S.I. accumulator discharge valves open.
MOV-841 Open MOV-865 Open Open breakers and leave fuses in for MOV-841 and 865.
MOV-841 Breaker Open MOV-865 Breaker Open Fuse In Fuse In 1500 psig plateau reached and inspection completed, If for ten year
- test, close PCV 430 isolation, MOV-516, 6
PCV-431C isolation valve MOV-515 upon reaching 2000 psig.
N/A other years.
MOV-516 Closed MOV-515 Closed
~ l
'l
'J
6.13 '
1 lg~dgd reached and inspection completed.
PT-7; 9 OF
- 6. 13. 5 If it is desired to verify leak tightness of MOV-516, perform the following:
6
~ 13
~ 5 ~ 1 6'3 '
Close MOV<<516 Open PCV-430 MOV-516 closed PCV>>430 open 6.13.5.3 Check MOV-516 for leakage:
6.13.5.4 Close PCV-430 6.13.5.5 Open MOV-516 PCV-430 closed MOV-516 open 6.13.5.6 Perform leakage calculation as follows:
PRT level:
Start e
Finish t
Delta level Time:
Start Finish Delta time min.
Obtain gallons per 4 level from PRT curve cha e
al delta time gpm gal/0
- 6. 13. 6 If it is desired to verify leak tightness of MOV-515, perform the following:
- 6. 13. 6. 1 Close MOV-515 6.13.6.2 Open PCV-431C
- 6. 13. 6. 3 Check MOV-515 for leakage 6.13.6.4 Close PCV-431C 6.13.6.5 Open MOV-515 MOV-515 closed PCV-431C open PCV-431C closed MOV-515 open 6.13.6.6 Perform leakage calculation as follows:
PRT level:
Start t
Finish S
delta level Time:
Start Finish delta time min.
Obtain gallons per 4 level from PRT curve chan e
al delta time gal/4
'h
PT-7'0 6 ~ 14 Leakage acceptance criteria for block valves:
o Less than 10 gpm - Continue operation o Greater than 10 gpm on one valve o Leakage acceptance criteria for PORV'B Tech Spec limits.
The volume control tank may not accommodate all the water on depressurization'o it may be necessary to either divert excess letdown to the Reactor Coolant Drain Tank or letdown through an orifice and divert to a
CVCS holdup tank.
After Hydro is completed or terminated, reduce system pressure to
<1500 psig by decreasing charging pump speed and/or HCV-123 controller output.
cAUTI0N:
~oo NO reduce Rcs pressure
<1000 peag until S.I. accumulators are isolated.
6.14.1 Close S.I. accumulator discharge valves MOV-865 MOV-841'
'4.2 6'4.3 6'4 '
Reduce system pressure to 350 psig.
Place switch to "ON" for P.I.-420 when system pressure is less than 700 psig.
If heatup is to continue and placing RER in service is not desired, mark steps 6.15.4-6.15.8 N/A.
If RSSP 1.1 is required, do not re-pressurize RHR system until test is completed.
At 350 psig, align overpressure protection system per 0-7, if RHR is to be placed in service.
6 ~ 15 When 350 psig is obtained, the RHR Loop may be cut in as follows:
6 ~ 15. 1 Maintain 350 psig as read on PR-420 or PI-420 using PCV-135.
II
Open orifice valves AOV-200A, AOV-200B and AOV-202.
Open Remove excess letdown system from service by closing HCV-123, making sure that PCV-135 is controlling pressure at 350 psig.
Close AOV 310, excess letdown stop valve.
AOV 310 Closed If RHR system is to be used, s]gw~ open HCV-133 to raise the RHR loop pressure to that of the low pressure letdown closely watching that primary system pressure is being controlled at about 350 psig as read on PR-420 or PI-420.
~SLOWL HCV-133 Open Open RHR loop isolation valves MOV-720 and MOV-721.
MOV-720 Open MOV-721 Open Open RHR loop isolation valves MOV-700 and MOV-701.
MOV-700 Open MOV-701 Open Open 738A 738B as needed to provide component cooling water.
Start an RHR Pump and maintain temperature by regulating flow through RHR Heat Exchangers using HCV-624, HCV-625 and HCV-626.
CAUTION:
RCS pressure must be maintained below 1992 psig until secondary side steam pressure is greater than 514 psig to prevent inadvertant Safety Injection actuation.
If hydro has been completed satisfactorily and system pressure
- reduced, block SI.
Return HCV-431K to normal setting, if changed.
Open MOV-516, if closed.
MOV-516 Open-
H,
PT-7: 12
- 6. 17. 2 Close the two (2) lower Reactor Head Vent solenoid valves.
SV-592 closed SV-593 closed 6 ~ 18 Consult with Operations Section as to whether RCS is to be returned to cooldown (via RHR) or if pressurizer bubble formation is desired.
6 ~ 19 If heat up is to
- continue, return to operating procedure O-l.l.
6.20
- 6. 20. 1 Notify Z&C to return steam generator pressure channels to normal as follows:
Place both steam header Atmospheric Relief Valves in Manual and closed.
6'0.2 I&C remove simulators from steam generator pressure channels simulated in step 6.1.2.
6'0.3 Place both steam header Atmospheric Relief Valves in Auto, if desired.
(N/A step if not desired).
6.21 Quality Control shall update the ISI program to reflect completion of this procedure.
QC COMPLETED BY:
DATE COMPLETED:
HEAD CONTROL OPERATOR:
QC SUPERVISZON REVIEW:
RESULTS
& TEST REVIEW:
SHIFT SUPERVISOR:
DATE DATE
~
4 PT-7: 13 (10 yr. only) 1500 2235 2352 (psig) 325 S
I 0
A VT-2 Visual Inspection of the Reactor Coolant System and items listed herein, shall be completed at the pressures indicated.
No leakage shall be allowed through
- pipe, vessels, or valve bodies.
Leakage through packing, flange gasketing, etc., shall be noted and quantified, if possible, for further evaluation by Operations or Plant Supervision.
1.0 PRESSURIZER 1.1 Safety valve inlet flange gaskets 1.2 Spray, valves 431A, 431B flange gaskets 1.3 Power operated relief inlet flange gaskets
- 430, 431C - MOV open 1.4 Valve packing 1.5 Heater connections 1.6 Manway 1.7 Vent flanges 2 '
REACTOR 2.1 Flange - Head Closure 2.2 Head Vent Flange 2.3 Conoseal Thermocouples (4) 2.4 Incore Seal Table 3 '
STEAM GENZRATOR 3.1 "A" Primary Inlet and Outlet Manway 3.2 "B" Primary Inlet and Outlet Manway 4 ~ 0 RESIIXJAL HEAT REROLL (RHR) 4.1 Valve 721 RHR discharge Loop "B" NODg:
Quantify leakage
(
)
5 ~ 0 MAINTENANCE ITEMS AS LISTED BY Q.C.
ENGINEER (Not Applicable steps may 5.1 5.2 5.3 5.4 5.5 5 '
5.7 5.8 5.9 5.10 be marked N/A.)
REMARKS
'nspected By:
Level II QC Inspector Date:
Reviewed By:
Operations Personnel QC Supervision Date:
j
r h4 T 7: 14 SYS NS A VT-2 Visual Inspection of the Reactor Coolant System and items listed herein, shall be completed at the pressures indicated, No leakage shall be allowed through
- pipe, vessels, or valve bodies.
Leakage through
- packing, flange gasketing, etc.,
shall be noted and quantified, if possible, for further evaluation by Operations or Plant Supervision.
2352 (psig) 1.
2 ~
3
~
4 ~
5.
6.
7 ~
8.
9.
10.
11.
12.
13.
14.
15.
16.
17.
18
'9.
20.
21.
22.
23
'4.
25.
26.
27.
28.
29.
30.
31.
32
'etdown line from RCS loop to orifices Excess letdown from RCS loop to HCV 123 Charging line fram Loop B hot leg to Regen.
HX Charging line from Loop B cold leg to Regen.
HX Charging line from check valve 370A to Regen.
HX Aux. spray line from charging line to pressurizer Alternate charging line from Loop A cold leg to AOV Loop A cold leg to Accum. discharge check 842B, S.I.
- 878J, and Accum test line to AOV 840B Loop B cold leg to Accum. Discharge check 842A, S.Z.
- 878G, and Accum. test line to AOV 839B Loop A hot leg to check valve 878H Loop B hot leg to check valve 878F Reactor vessel to MOV 852A Reactor vessel to MOV 852B Loop A hot leg to MOV 701 Loop B cold leg to MOV 720 Loop A drain to Valve 503 Loop B drain to Valve 540 Press.
licgxid space sample line to AOV 953 A loop hot leg to Valve 998 B loop hot leg to AOV 955 Incore penetrations in Sump A A loop instrumentation lines B loop instrumentation lines Pressurizer instrumentation lines Mini spray line around PCV 431A Mini spray line around PCV 431B Pressurizer to B loop hot leg surge line Pressurizer steam space sample line to AOV 951 Rx head to head vent valve branch connection Control rod drive penetrations Pressurizer heater connections Check all accessible ma)or components for leakage (i.e.
Rx Vessel, Steam Generators etc.) within the Reactor Coolant System boundary, which were not mentioned in preceding steps 392B check check REMA'(S:
Inspected By:
Level ZZ Q.C. Inspector Date:
Reviewed By:
Operations Personnel QC Supervision Date:
T
ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION PORV BLOCK VALVE REPLACEMENT PROGRAM ATTACHMENT C.11 MOVATS Motor Operated Valve Database Summary Table
0
ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION PORV BLOCK VALVE REPLACEMENT PROGRAM ATTACHMENT C.11 MOVATS Motor Operated Valve Database Summary Table MEASURED VALUES
-- ~ ---PARAMETERS------
X Y
VALVE DATA USED TO EXTRAPOLATE DP THRUST REQUIREMENTS FOR MOV 515 AND MOV 516.
PARALLEL DISK CATE VALVES.
CLOSE TO OPEN MOVATS DATABASE ORIFICE RBC NO MANU
- DIA, DIFF PRES X
DP ORIFICE AREA THRUST a
~
a r 0
1000 2600 2600 2600 2610 2850 o
o o a o o a o r o ~
a a
o r a ~
Oaooo 0
0 76 AD 2.750 5937 5115 144 AD 2.750 15435 4348 42 AD 2.750 15435 4401 38 AD 2 750 15435 6746 69 AD 2.750 15494 2766 41 AD 2.750 16919 2931 OPEN TO CLOSE MEASURED VALUES
~ -PARAMETERS-------
X Y
MOVATS ORIFICE STEM DATABASE DIA DIA REC NO MANU in in LINE
~ 3 X DP X DP PRESSURE ORIFICE AREA +
psi psi LP X STEM AREA THRUST lbs 0.000 75 AD 2.750 143 AD 2.750 39 AD 2.750 38 AD 2.750 42 AD 2.750 69 AD 2.750 84 AD 2.750 0.000 1 '50 1.250 1.250 1.250 1.250 1.250 1,250 0
1000 2600 2600 2600 2600 2610 2750 0
1000 2600 2600 2600 2600 2610 2750 0
0 3008 jJ 714 7820 5401 7820 6343 7820 8947 7820 9185 7850 7495 8271 5004
ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION PORV BLOCK VALVE REPLACEMENT PROGRAM ATTACHMENT C.12 Gilbert/Commonwealth, Inc. calculation, "PRV Block Valve Thrust Calculation"
1 lm'
~