ML18142A719
| ML18142A719 | |
| Person / Time | |
|---|---|
| Site: | Ginna  (DPR-018) |
| Issue date: | 08/04/1977 |
| From: | Amish K Rochester Gas & Electric Corp |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18142A719 (62) | |
Text
U.S. NUCLEAR REGULATORV COM cION NRC FCRM 195
/
I2.7BI S.
NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL DOC~ET NUMBER
~0 RQ FILE NUMBER TO:
Mr. Ai Schwencer FROM:
Rochester Gas
& Electric Corp.
Rochester, New York Keith W Amish DATE OF DOCUMENT 8/4/77 DATE RECEIVED 8/8/77 ETTE R QORIGINAL Qcopv DESCRIPTION QNOTORIZED Q UN C LASS I F I E D PROP INPUT FORM ENCI.OSU RE NUMBER OF COPIES RECEIVED Attachment A: Response to questions from NR on applicantIs proposed Inservice Pump and Valve Testing Program.
Attachment B: Consists of a revised program, Appendix C, Revision 1,. of the Quality Assurance'anual entitle+'<Qiqna Station Inservice Pump,Iagd)gak>+LLe~iIng Program for the Sept, 1,
f;977<ttL'ougfi May 31, 1979 PLANT NAME: Ginna Unit No 1
RJL 8/8/77 (29-P)
FOR ACTION/INFORMATION ENVIRHNMENTAL ASSIGNED AD!
V MOORE LTR BRANCH CHIEF.
PROJECT MANAGER.
LICENSING ASSISTANT:
INTERNALD YFMS SAFETY HEINEMAN E
ER Bi HARLESS R IBUTION IST PLANT SYSTEMS TEDESCO BENAROYA SITE SAFETY &
ENVIRON ANALYSIS DENTON & MULLER ENGINEERING IPPOLITO OPERA ING REACTORS ENVIRO TECH ERNST BLO D BAER B
ER GAMMILL 2
TIC RE IV J HANCHETT CHECK AT I ALTZMAN ERG EXTERNALDISTRIBUTION NSIC SITS ANALYSIS VOLLMER BUNCH Ji COLLINS KREGER CONTROL NUMBER
))jIW 772200244 16 CYS ACRS SENT CAT GO Y
~)NRC FORM 195 (2-781
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TOtE j Ittn
'ROCHESTER GAS AND ELECTRIC CORPORATION
~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649
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KEITH W, AMISH EXECUTIVE VICE PRESIOEHT TCLCPHONC
~@gy(yy DXI(',D-F1LE COPY August 4, 1977 Director of Nuclear Reactor Regulation Attention:
Mr. A. Schwencer, Chief Operating Reactors Branch 41 U.
S. Nuclear Regulatory Commission Washington, D.C.
20555 4 ed
Subject:
Inservice Pump and Valve Testing R.
E. Ginna Nuclear Power Plant, Docket No. 50-244 Program Unit Nl Gentlemen:
This letter is in response to questions from members of your staff on our proposed Inservice Pump and Valve Testing Program as submitted by our letter of April 6, 1977.
Our responses to'he questions are presented in Attachment A to this letter.
In addition, as a result of our review in prep-aration of the responses, the need for several other changes became apparent.
These changes are also described in Attach-ment A.
A r'evised program, Appendix C, Revision 1, of the Ginna Station Quality Assurance Manual entitled HGinna Station Inservice Pump and Valve Testing Program for the September 1,
1977 through May 31, 1979 Period" is presented in Attachment B
for your information.
Forty (40) copies of this letter and the Attachments are provided for your use.
Very truly yours, Keith W. Amish Attachments
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Attachment
'A Res onse to NRC Questions'.
Provide additional information to describe exactly why the service water system will not allow a reference flow rate to be established and subsequent flow rate measurements to be taken at the same condition and compared to the reference value.
We have reviewed the testing methods and have determined Chat, the service water pumps can be tested monthly.
2.
One of the Section XI requirements is to measure the maximum valve stroke time of. power operated category A and B valves.
The pump and valve testing program for Ginna does not, address this requirement.
Indicate whether you intend to meet this requirement and if so, you should incorporate it into the program submittal.
Stroke time 'for power operated category A and B valves will be timed during each test by means of switch initiation and-indication lights on the main control board.
During testing in refueling conditions, physical verification of stem position will be confirmed in addition to the timing.
Use of the switch initiation and indication lighCs will provide accurate times since there are no inherent time delays built into the electronic circuitry.
3.
Article IWV of Section XI requires valve testing at cold shut-down intervals when testing during normal operation might compromise plant safety.
Provide justification for testing at refueling intervals rather than at cold shutdown intervals, for each category A and B and category C check valves, where
, refueling intervals are specified as the test frequency in the valve-test program.
Refueling intervals were specified instead of cold shutdown because cold shutdowns occur only infrequently between refuel-ing outages and are usually of too short duration for the required tests to be performed.
It was not felt to be warranted to require an extension of a cold shutdown, solely for the pur-pose of completing a valve testing program when no such testing would have been required had there not been that cold shutdown.
It has been estimated that it would require approximately four days to complete all tests which must be performed at cold or refueling shutdown, assuming there are no other significant demands on testing personnel during that time and that systems.
that contain radioactive fluid and must be drained for testing
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can be promptly drained.
- Because there exists a possibility for an extended cold shutdown at atime when these valves are due to be tested, i.e'., after the quarter has expired, test personnel will attempt to have completed all required tests if a cold shutdown extends to more than four days.
For cold shutdowns of lesser duration, a lesser number of valves will be tested.
For very short cold shutdowns, it is expected that no valves would be tested due to the length of time that is required to notify the required personnel and initiate a testing program under proper procedural control.
4.
Provide justification for testing valve 427 at refueling intervals instead of at 3 month intervals as required by Article INV of Section XI.
Testing valve 427 during normal plant operation would interrupt the letdown (CVCS) system flow.
"Note 3" should be entered in the "Note" column for valve 427.
5.
Provide information to justify why an exercising test cannot be performed on valves 878G and J during normal operation by observing the flow or monitoring the pressure at the flanged drain or test line located downstream of these valves.
Valves 878G and J could be tested during normal operation by starting a safety injection pump and pressurizing the affected portion of piping to greater than the accumulator pressure (greater than 700 psig).
Drain valves 2844 or 2835 could then be opened and flow or pressure monitored at the flanged drain.
The drain valve could then be closed and the safety injection pump shut down.
Several difficulties present themselves with this test.
First, care must be taken so that the accumulator is not discharged through the drain line. Secondly, a distinct possibility exists that in the process of opening the drain valve, the seat will be cut.
Although a swage lock fitting exists downstream of the drain valve, it is not intended to be the system boundary.
Repairs to the drain valve could not be'ccomplished without isolating the associated accumulator.
In addition, if a safety injection were to occur during the time, the drain valve was open, some of the water assumed to inject into the reactor vessel would be lost through the drain valve.
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Valves 878F and 878EE are identified in the relief request basis but are not listed in the program text.
Provide in-formation to clarify whether you intend to test these valves or to ask for relief from the Section XI requirements.
Valves 878F and 878H, check valves in the safety injection lines to the reactor hot legs, have no safety function since hot leg safety injection is never required.
The valves were inadvertently added to a note in the relief basis and have been removed.
7.
Relief from testing valves 866A and 866B, is requested because a flow test would douse the charcoal filters and render them inoperable.
Provide a description of the exact safety related function of these valves and the consequences of their failure to operate within their design function.
What other methods of determining valve operability have you considered?
The safety function of post accident charcoal filter dousing system is described in Section 6.3 of the Ginna FSAR.
In the event of a Design Basis Accident which releases radioactive material to containment, the containment, fan-coolers would supply containment atmosphere to the post accident charcoal filters. If, after some period of operation, the fan-cooler supplying a post accident charcoal filter were to fail, forced flow through the filter would cease.
,Fission products deposited on the filter would cause the filter to begin to slowly heat, up.
As described in the FSAR, however, loss of a fan motor would not result in ignition of the charcoal.
Ignition could be prevented by backflow induced by the other fans.
The dousing system is, therefore, an additional means of ensuring that even if ignition were to occur, a fire could be extinguished.
The check valves 866A and 866B cannot, be tested by supplying water to the line since such a test would require actuation of containment spray, and would result in borated water being sprayed throughout containment.
It would also result in borated water being trapped at the motor operated valves above the filter dousing system spray nozzles which could result in degradation of the piping or valves.
A test could be perfoxmed by supplying,air to the open containment spray ring header.
- However, at, this time there is no instrumentation provided which would provide the data needed to ensure check valve operability.
Because the dousing system might be required to perform a safety function, the dousing system piping will be modified to enable testing of the two check valves.
Because of the long lead times for
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t equipment, such as valves, which is'qualified for a seismic category I system, it is unlikely that such a modification can be accomplished at. our spring 1978 refueling outage.
We will, however, install the necessary modifications during the spring 1979 outage and will commence the required testing at, that time.
Thus valves 866A and 866B have been added to category C of the program+
8.
Provide information to identify the redundant isolation valves that serve the same isolation function as valves 528 and 529.
Identify whether you intend to test these valves or to ask for relief from the code requirements.
There is no redundant valve serving the same isolation function as valve 528.
This configuration is fully described in the Ginna FSAR in Section 5.2 (see page 5.2.2-1, Table 5.2.2-1, and Figure 5.2.2-1).
The redundant valve for valve 529 is valve 508, which is presently included in the program.
9.
Relief is requested for valve 3838 of the cvcs system (Drawing ii7o. 33013-433C) from the exercising test requirement during normal plant operation because of a thermal shock consideration.
Provide information to justify that the test connection, shown in the drawing 33013-433C, cannot be used to test this valve.
The test connection shown in drawing 33013-433C could be used to test valve 383B and avoid thermal shock to the inlet nozzle in the primary loop.
- However, use of this test connec-tion during normal plant operation would result in radiation exposure to test personnel which is not warranted.
A recent survey in the vicinity of the test connection for valve 383B indicated a neutron field of 500 mr/hr and a gamma field of 250 mr/hr.
Each test could require one to perhaps two hours in this environment.
Thus, it is proposed that testing of valve 383B not be required during plant operation.
10.
Relief is requested for valve 351 of the cvcs system (Drawing No.
33013-433C) from the exercising test requirement during normal plant operation because of the potenti'al for the boric acid solution setting up.
Provide additional-information, in detail, to clarify this request for relief including approxi-mate times involved for the solution to set up and the condi-tions which would cause this event.
Also why the normal flush-ing system cannot be used following a test, to prevent the boric acid solution from setting up.
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Valve 351 is not required to perform a safety function, should not have been included in the program and therefore has been removed.
The immediat'e borate function is an operator initiated procedure which may be used to rapidly borate the primary system.
However, its functioning has not been assumed in the safety 'analysis.
In addition, for the same reasons, valve 350 should be deleted.
Additional Chan es During the preparation of the above responses, it became apparent that several other changes should be made in the program.
These are enumerated below:
Valves 841 and 865, isolation valves in the accumulator dump lines, should be deleted from the program.
In accordance with Technical Specification 3.3.1.1.g, these valves are disabled in the open position.
They are not. required to be closed to per-form a safety function.
During a normal plant shutdown to cold shutdown, without safety injection, the valves are closed to prevent, unnecessary discharge of the accumulators to the primary system.
2.
Valves 878B and 878D, motor operated valves on the safety injection lines to the cold legs, should be deleted.
In accor-dance with Technical Specification 3.3.1.1.g,,these valves are disabled in the open position.
They are not required to be closed to perform a safety function.
3.
Valve 879, a manual valve in the safety injection test line, is not required to, change position to perform a safety function.
The only requirement is that leakage through valve 879 be acceptably low.
Therefore, the quarterly stroke test requirement for valve 879 has been deleted.
4.
Valves 1816A and 1816B, manual valves in the supply line from the lA RHR heat exchanger to the 1C safety injection pump, should be deleted.
This line provides additional paths for water for high head recirculation, but is not assumed to be operable in any of the plant safety analyses.
Therefore, it is not required to perform any function to mitigate the consequences of an accident.
5.
Valves 780A and 780B, manual butterfly valves in the component cooling w'ater supply to the RHR heat exchangers, should be.
deleted.
These valves were provided to balance the flow to the RHR heat exchangers.
They are now pinned in place and are not required to change position or serve any safety function.
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Power operated relief valves 430 and 431C should be deleted inasmuch as they are not required to perform a safety function.
They are provided only to avoid operation of the pressurizer safety valves.
Three valves, 896A and B and 856, are in the supply lines for the safety injection system from the refueling water storage tank.
In accordance with Technical Specification 3.3.l.l.g, all three are locked in the open position.
At present, Technical Specification 4.5.2.2.a requires that these valves be tested at least once per month.
However, since failure of any of the valves in a closed position would prevent water from being supplied to the safety injection pumps (896A or B) or to the residual heat removal pumps (856), it is proposed that 0he pump and valve testing program only require testing at cold/re-fueling shutdowns.
In addition, a Technical Specification change will be requested which would either delete this testing requirement from the Technical Specifications or make the Technical Specifications consistent with the pump and valve testing program.
This change will be submitted by September 20, 1977.
Valves 825A and B are required to open during safety injection after the water level in the boric acid tanks reaches a low level setpoint.
If either 825A or B were open at the time of a safety injection signal, an open path would exist between the refueling water storage tank and the boric acid tanks.
This would result in overflowing the boric acid tanks and loss of that tank's 12 percent boric acid solution.
Therefore, it is proposed that these valves be tested only during cold/refueling shutdowns.
Air piston valves
- 5871, 5872,
- 5873, 5874,
- 5875, and 5876, containment post accident charcoal filter isolation valves, should be added to category B of the valve test,ing program.
These valves are required to open on a safety injection signal and would provide for containment air flow from containment fan-coolers to containment post accident chaxcoal filters.
'ir piston valves 81, 82, 83, 84, 85 and 86,control room ventila-tion isolation valves, should be added to category B of the pro-gram.
These valves are required to operate on a high radiation signal in the control room ventilation system so that doses to control room personnel following a design basis accident are maintained acceptably low.
Air piston valves
- 5869, 5870, 5878 and 5879, containment purge isolation valves, should be added to category A of the program.
These valves are required to operate on receipt of a safety injection signal.
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Attachment QUALITY.ASSURANCE MANUAL SECT. NO.
R EV.
40 OOA PAGE 1
GF 23 EFF ECTIVE OATE ISeptember 1,
1977 SIGNATURE ROCHESTER GAS 6 ELECTRIC CORPORATION
'INNA STATION DATE TITLE APPENDIX C Ginna Station Inservice Pump and Valve Testing Program for the September 1,
1977 Throu h Ma 31 1979 PerLod PREPAREO BY:
REVIEITEO BY:
APPROVED BY:
4 gv/~p Pro ram Table of Contents
==
Introduction:==
Discussion Definitions:
Program:
PVT 1.0 Scope and Responsibility PVT 2.0 Code Edition and Testing Interval PVT 3.0 Inservice Pump Testing Program PVT 4.0 Inservice Valve Testing Program PVT 5.0 Records
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QUALITYASSURANCE MANUAL GINNA STATION APPENDIX C Ginna Station Inservice Pump and Valve Testing'rogram for the September 1,-"1977 Through Ma 31',
1979 Period DATE 40 OOC Sept.
1, 1977 PAGE oF 23 Introduction This appendix to the Quality Assurance Manual defines the Inservice Pump and Valve Testing Program for the twenty month period starting September 1,
1977 through April 30, 1979.
Included in this program are the Quality Groups A,
B and C Pumps which are provided with an emergency power source and those Quality Groups A, B and C Valves which are required to shut down the reactor or to mitigate the consequences of an accident and maintain the reactor in a safe shutdown condition.
This program has been developed as required by Section 50.55(a)(g) of 10CFR50 following the guidance of the ASME Boiler and Pressure Vessel Code Section XI "Rules for Inservice Inspection of Nuclear Power Plant Components,"
(hereat'ter referred to as the "Code" ) excluding the controls of the Authorized Inspector, Enforcement Authority, Report-ing Systems and N-Stamp Symbol.
The inservice testing pro-gram shall be controlled by the Ginna Station Quality Assur-ance Program for Station Operation.
Quality Groups A, B and C components correspond to those defined in NRC Regula-tory Guide 1.26.
Further addenda and editions of Section XI of the Code shall be used for clarification of test requirements and performance.
The'Inservice Pump and Valve Testing Program does not affect the pump and valve surveillance program required by Technical Specifications.
Technical Specification re-quirements shall continue to be implemented at the required frequency.
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QUALITYASSURANCE MANUAL GINNA STATION TITLE APPENDIX C Ginna, Station Inservice Pump" and Valve Testing Program for the September 1,
1977 Through Ma 31, 1979 Period DATE Sept.
1, 1977 PAGE oF 23 Definitions AFP AOV APV BA Code CC CK CS CSP CV C/R ECCS FCV GA GDT HCV HX LCV MDAFP MOV MV PCV PIV PRT PVT '
R RCDT RCP RCV RHR RMW RV RWST RX S/G SI SIV SW TDAFP TK VC VCT VH Auxiliary Feedwater Pumps Air Operated Valve Air Operated Piston Valve Boric Acid American Society of Mechanical Pressure Vessel Code Component Cooling Check Containment Spray Containment Spray Pump Check Valve Cold Shutdown or Refueling Emergency Core Cooling System Flow Control Valve Gas Analyzer Gas Decay Tank Hand Control Valve Heat Exchanger Level Control Valve Motor Driven Auxiliary Feedwat Motor Operated Valve Manual Valve Pressure Control Valve Primary Isolation Valve Pressurizer Relief Tank Pump and. Valve Testing Quarterly Refueling Outage Reactor Coolant Drain Tank Reactor Coolant Pump Radiation Control Valve Residual Heat Removal Reactor Makeup Water Relief Valve Refueling Water Storage Tank Reactor Vessel Steam Generator Safety Injection Secondary Isolation Valve Sexvice Water Turbine Driven Auxi,liary Feed Tank Volume Contxol Volume Control Tank Vent, Header Engineers Boiler and er Pump Pump
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QUALlTY ASSURANCE MANUAL GINNA STATION TITLE APPENDIX C Ginna St'ation Inseryice Pump and Valve Testing Program for the September 1,
1977 Through Ma 31 1979 Period OATE Sept.
1, 1977 PAGE 4
oP 23 Pum and Valve Testin Pro ram PVT 1.0 Sco e and Res onsibilit The inservice testing program defines the testing pro-gram for Quality Groups A, B and C Pumps and Valves in accordance with the requirements of Articles IWP and IWV of Section XI of the Code.
The results of these tests are to assure the operational readi-ness of pumps and valves.
1.2 It is the responsibility of the Ginna Station Test and Results Engineer to implement,this test pro-gram and develop inservice test procedures which will outline the specific test for each pump and valve included in the program.
1.3 After preventative or corrective maintenance the affected pumps or valves shall be tested to reestablish any reference values and assure operability.
PVT 2.0 Code Edition and Testin Interval 2.1 The Inservice Pump and Valve Testing, Program for the twenty (20) month period starting September 1,
1977 through April 30, 1979 was developed utilizing the 1974 Edition of Section XI of the Code through the
.Summer 1975 Addenda.
- 3. 0 Inservice Pum Testin Pro ram 3.1 The Inservice Pump Testing Program was developed in accordance with the requirements of Article IWP of Section XI of the Code.
This program includes all Quality Group A, B and C pumps which are provided with an emergency power s'ource and are required to safely shut down the reactor or to mitigate the consequences of an accident and maintain the reactor in a safe shutdown condition.
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QUALITYASSURANCE MANUAL GINNA STATION TITLE APPENDIX.C Ginna,,Station Inservice Pump and Valve Testing Program for the September 1,
1977 Thxough Ma 31 1979 'Period OATE 4+ 90C OF 23 Sept.
1, 1977 PAGE 3.2 The ollowxng pumps shall e t:ested in accordance with Article IWP of Section XI:
(a)
(b)
(c)
(d)
(e)
(f)
(g)
(h)
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(p) lA Component: Cooling 1B Component Cooling lA Safety Injection 1B Safety Injection 1C Safety Injection lA Residual Heat Removal lB Residual Heat Removal lA Containment Spray lB Containment Spray lA Auxiliary Feed 1B Auxiliary Feed Turbine Driven Auxiliazy Feed 1A Service Water 1B Service Water 1C Service Water 1D Service Water 3.3 PVT 4.0 4.1 4.2 Flow rates will not be accurate for the residual heat removal pumps because the bypass test loop can only pass 200 gpm.
This bypass test loop is a fixed resistance system; therefore, hydraulic resistance remains unchanged from test to test.
Insexvice Valve Testin Pxo ram The Inservice Valve Testing Pxogram was developed in accordance with the requirements of Article IWV of Section XI of the Code.
All those valves that are required to perform a safety function either to shut down the reactor or to mitigate the con-sequences of an accident and maintain the reactor in a safe shutdown condition are included in the program+
The Inservice Valve Testing Pxogram Requireme'nts for Category A and B Valves are found in Tables PVT 4.7 and 4.8, respectively.
Category,C Valves are broken down into two categories, Check Valves and, Relief Valves, which are found in Tables PVT 4.9 and 4.10, respectively.
Category D Valves are not included in this testing program because there are none included in Ginna Station design.
Category E Valves are not listed because there axe not any applicable test:ing requirements.
During opexation Category E Valves are monitored to verify that they are locked.
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QUALITYASSURANCE
'ANUAL GINNA STATION APPENDIX C Ginn'a.Station Inseryice Pump and Valve Testing Program for the September 1,
1977 Through Ma 31 1979 Period DATE Sept.
1, 1977 PAGE DF 23 4.3 Some exceptions and exemptions to the testing re-quirements of Article IWV have been taken based on operational interference, placing the plant in an unsafe condition and Technical Specification requirements.
All exceptions and exemptions are listed on the valve tables and explained in the referenced
- notes, PVT 4.11.
4 ~ 4 4.5 4.6 The exercising program for Category A and B Valves, with the exception of check valves, shall require a complete stroking of each valve per the valve testing tables.
All check valves, including Category C Valves, shall be exercised to the posi-tion required to fulfilltheir function.
These functional tests shall be verified by the operation of the required system.
Category A and B valves operation shall be timed each time they are stroked utilizing switch initiation and the position indicators, which are accessible during plant operation.
During each refueling outage a visual verification shall be made to confirm direct correspondence between valve operators and the position indicators.
The testing of valves required at. cold shutdown or refueling outages will normally take four (4) days to complete.
When cold shutdowns are of a shorter duration, test. personnel shall attempt to test as many valves as possible without holding up the start-up of the unit.
For very short. cold shutdowns, it would be impossible to mobilize test personnel to
'implement the testing program under the required'roceduxal controls, therefore no valves would be tested.
It is possible that, during a foux (4) day cold shutdown, the work load on test personnel may preclude their completion of all the required valve tests prior to startup.
Valve testing duxing cold shutdowns shall not be more frequent than one test per quarter for each valve in the test. program.,
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QUALITY ASSORANCE MANUAL G INNA STATION TITLE APPENDIX C Ginna Station Inservice Pump -and Valve Testing Program fox the September 1, 1977 Through Ma 31
~1979 Period-OATE Sept.
1, 1977 PAGE OF 4.7 Category A Valves Valve I T~e Note Test Fxece 304A CV 304B 37OB 371 I
3838 508 528 529 539 743 745 750A 750B 1-A RCP Seal Injection Check 1-B RCP Seal Xnjection Check MOV CV Seal Water Return Isolation Charging Line Xsolation Valve AOV Letdown Isolation CV Alternate Charging Line Check AOV RMW to Containment Vessel Stop CV N2 Supply to PRT CV RMW to PRT AOV PRT Stop Valve to Gas Analyzer CV CC From Excess Letdown HX.
AOV CC Return From Excess Let-down HX.
CV CK CC to A RCP CV CK CC to B RCP Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak Stroke Leak C/R R
C/R R
C/R R
C/R R
C/R R
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QUALITY.ASSU RANC E MANUAL GINNA STATION TITLE:
ff APPENDIX C Ginna Station Inservice Pump and Valve Testing Pxogram "for the Sept++b$ r l~.jg77 T~gu9h OATE 49 QOC Sept.
1, 1977 PAGE 8
oF 23 759B MOV 813 MOV 814 MOV Valve N
~Te 759A MOV Des'cri tion Containment Stop CC From Loop A RCP Containment Stop CC From Loop B RCP Supply CC to RX Support Cooling Return CC to RX Support Cooling Note Test F~xe 5
Stroke C/R Leak R
5 Stroke C/R Leak R
6 Stroke C/R Leak R
6 Stroke C/R Leak R
846 862A 862B 870A 870B 879 889A 889B AOV N2 Supply to Accumulators CV 1-A CSP Disch Check CV 1-B CSP Disch Check CV 1-A to 1-C SI Pump Disch Check CV 1-B to 1-C SI Pump Disch Check MV SI Test. Line Isolation h
CV 1-A SI Pump Disch Check CV 1-B SI Pump Disch Check Stroke Q
Leak R
Stroke Q
Leak R
Stroke Q
Leak R
Stroke Q
Leak R
Stroke Q
Leak R
Stroke Leak R
Stroke Q
Leak R
Stroke Q
Leak R
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QUALITYASSURANCE MANUAL.
GINNA STATION TITLE:
APPENDIX C Ginna,. Station Inservice Pump and Valve Testing Program for the September l~ 1977 T~ough Ma 31 i979 Period DATE 19 QOC Sept.
1, 1977 PAGE OF 23 Valve N
~Te 966A AOV Descri tion Pressurizer Steam Space VC 966B 966C AOV AOV Pressurizer Liquid Space VC Isolation Valve Loop A and B Hot Leg VC Isolation Valve 1003B LCV 1-B RCDT Pump Suction 1713 CV N2 to RCDT CV 1721 AOV Suction line to RCDT 1723 AOV A Containment Sump Disch Stop Valve to Waste Holdup Tank 1003A LCV 1-A RCDT Pump Suction Note Test F~Fre Stroke Q
Leak R
Stroke Q
Leak R
Stroke Q
Leak R
Stroke Q
Leak R
Stroke Q
Leak R
Stroke Q
Leak R
Stroke Q
Leak R
Stroke Q
Leak R
1728 AOV A Containment Sump Disch Stop Valve to Waste Holdup Tank Stroke Q
Leak R
1786 1787 AOV SIV RCDT to VH AOV PIV RCDT to VH Stroke Leak Stroke Leak Q:
R Q
R 1789 AOV ISO Valve Outlet RCDT to GA
Stroke Leak Q
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QUALITY ASSURANCE MANUAL G INNA STATION TITLE APPENDIX C Ginna Station Inservice Pump and Valve Testing Program for the September, 1
1977 Through May 31', i979 Period 10 OF 23 DATE Sept.
1, 1977 PAGE Valve N
T~e Descri tion Note Test F~re 5869 5870 5878 5879 APV Containment Purge Supply Isolation APV Containment Purge Supply Isolation APV Containment Purge Exhaust Isolation APV Containment Purge Exhaust Isolation Stroke Q
Leak R
Stroke Q
Leak R
Stroke Q
Leak R
Stroke Q
Leak R
4.8 Category B Valves Valve N
~Te Descri tion 014 017 081 RCV Aux Building GDT Release RCV Comp Cool Surge TK Vent Control Room Ventilation Damper Note Test F~re Stroke Q
Stroke Q
Stroke Q
082 083 084 085 086 112B 112C Control Room Ventilation Damper Control Room Ventilation Damper'ontrol Room Ventilation Damper Control Room Ventilation Damper Control Room Ventilation Damper Emergency Makeup RWST to Charging Pump LCV VCT Outlet Stroke Q
Stroke Q
Stroke Q,
Stroke Q
Stroke Q
Stroke Q
Stroke Q
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QUALITYASSURANCE MANUAL GINNA STATION TITLE APPENDXX C Ginna Station Inservice Pump and Valve Testing Pxogram for the September 1,
1977 Thxough Ma 31 1979 Period OATE 49 OOC Sept.
1, 1977 PAGEll oF 23 Valve I
~Te Descri tion 427 624 625 626 700 MOV Suction Stop From Loop A to RHR Pumps AOV Letdown From Loop B HCV 1-B R HR HX Outlet HCV 1-A R HR HX Outlet FCV RHR Loop Return Note
- Test, Frece 3
Stroke C/R Stroke Q
Stroke Q
Stroke Q
8 Stroke C/R 701 MOV Suction Stop From Loop B to RHR Pumps-8 Stroke C/R 70 4A 704B 720 MOV Motor Operation Pump Disch to RHR Pumps MOV Suction 1-A RHR Pump MOV Suction 1-B RHR Pump Stroke Q
Stroke Q
8 Stroke C/R 721 723A 723B MOV CV CV Motor Op 10" Disch to B Loop From RHR Pumps Discharge Check Valve 1-A CC Pump Discharge Check. Valve 1-B CC Pump 8
Stroke C/R Stroke Q
Stroke Q
738A 738B MOV CC to 1-A RHR HX MOV CC to 1-B RHR HX Stroke Q
Stroke Q
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QUALITYASSURANCE MANUAL GINNA STATION TITLE APPENDIX C Ginna Station Inseryice Pump and Valve Testing Program for the September 1,
1977 Through DATE 49 90C Sept.
1, 1977 PAGE 12 23 alve N
~Te 825A MOV SX Pump Suction From RWST Note Test Fleece li 9
Stroke C/R 825B 826A 826B 826C 826D MOV SX Pump Suction From RWST MOV SI Pump Suction From BA Tank MOV SI Pump Suction From BA Tank MOV SX Pump Suction From BA Tank MOV SI Pump Suction From BA Tank 9
Stroke C/R Stroke Q
~
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Stroke Q
Stroke Q
Stroke Q
836A 836B HCV HCV Spray Additive Tank Dis-charge Spray Additive Tank Dis-charge Stroke Q
Stroke Q
850A 850B 851A 851B 852A 852B MOV Sump B to RHR Pumps MOV Sump B to RHR Pumps MOV Xn Sump B to RHR Pumps MOV
. In Sump B to RHR Pumps MOV RHR Pump to RZ Vessel MOV RHR Pumps to RX Vessel Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
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QUAL'ITY ASSURANCE NIANUAL GINNA STATION TITLE APPENDIX C Ginna Station Inservice Pump and Valve Testing Pxogram for the September 1'977 T~ough May 31,'979 Pere.oct 13 23 DATE Se t. 1, 1977 PAGE Valve N
~Te Descxi tion I 856 857A MOV Isolate 41 RHR HX From CS and SI Pumps MOV EST to RHR Pumps Note Test Fleece 9
Stroke C/R Stroke Q
857B 857C 860A 860B 860C 860D MOV MOV MOV MOV MOV MOV Isolate N2 RHR HX From CS and SI Pumps Isolate Nl RHR HX From CS and SI Pumps Parallel Discharge MOV From 1-A CSP Parallel Discharge MOV From 1-A CSP Parallel Discharge MOV From 1-B CSP Parallel Discharge MOV From 1-B CSP Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
871A MOV 1-A to 1-C SI Pump Discharge
Stroke Q
871B 875A 875B 876A 876B MOV MOV MOV MOV MOV 1-B to 1-C SI Pump Discharge Parallel MOV From CS Pumps to Charcoal Filter Deluge Parallel MOV From CS Pumps to Charcoal Filter Deluge Parallel MOV From CS Pumps to Charcoal Filter Deluge Parallel MOV From CS Pumps to Charcoal Filter Deluge Stroke Q
II Stroke Q
Stroke Q
Stroke Q
Stroke Q
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QUALITY ASSURANCE MANUAL GINNA STATION APPENDIX C Ginna Station Xnservice Pump and Valve Testing Program for the September 1, 1977 Thxough Ma 31, 1979 Period 14 or-23 DATE Sept.
1, 1977 PAGE Valve I
~Te 896A 896B 1815A MOV RWST to CS and SX Pumps MOV RWST to CS and SX Pumps MOV C-SX Pump Suction From RWST Note Test F~re 9
Stroke C/R 9
Stroke C/R Stroke Q
1815B 3504 3505 3652 3996 4000A 4000B 4000C 4000D 4007 4008 4013 MOV C-SI Pump Suction From RWST MOV Main Steam to AFP From 1-B S/G Remote Valve MOV Main Steam to AFP From 1-A S/G Remote Valve MV Main Steam Throttle Valve to TDAFP MOV TDAFP Discharge Valve MOV Cross Over Valve For MDAFP MOV Cross Over Valve For MDAFP CV 1A MDAFP Dischaxge Check Valve Downstream MOV-4007 CV lB MDAFP Discharge Check Valve Downstream MOV-4008 MOV 1-A MDAFP Discharge Valve MOV 1-B MDAFP Discharge Valve MOV TDAFP Service Water Supply Isolation Valve Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q'
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QUALITYASSURANCE MANUAL GINNA STATION TITLE APPENDIX C Ginna Station Xnservice Pump and Valve Testing Program for the geptemb~g 1~ )[77 Though OATE 40 OOC Sept.
1, 1977 PAGE 15 23 4027 MOV Valve N
~Te Descri tion 1-A MDAFP Service Hater Isolation Valve Note Test Fleece Stroke Q
4028 4098 MOV 1-B MDAFP Service Hater Isolation Valve Service Mater Supply Iso-lation to TDAFP Stroke Q
Stroke Q
4291 4297 AOV TDAFP Recir. Line AOV AFN Reg. Discharge Valve to 1-A S/G Stroke Q
Stroke Q
4298 4304 4310 4561 4562 4609 4613 4614 4615 AOV AOV AOV AOV AOV MOV MOV MOV MOV Aux.
FW Reg. Valve Dis-chaxge to 1-B S/G 1-A MDAFP Recirculation Cont. Valve 1-B MDAFP Recirculation Containment Valve Containment Vent Recirc.
Fans Dischaxge Flow Con-trol Valve Containment. Vent Recirc.
Fans Discharge Flow Con-trol Bypass Valve 1-Al Intake Screen Nash Isolation Valve 1-B2 Turbine Building SN Xsolation Valve 1-Al Turbine Building SW Xsolation Valve 1-Bl Aux. Building SN Xsolation Valve Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke.
Q Stroke Q
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QUALITYASSURANCE MANUAL GINNA STATION TITLE APPENDIX C Ginna Station
'Inservice Pump and Valve Testing, Program for'he saptemh)y l~ $/77 TIm'pugh OATE Sept.
1, 1977 PAGE 16 or-23 4616 MOV 4663 MOV Valve ¹ T~e Descri tion 1-Al Aux. Building SW, Isolation Valve to CC HX Air Condition Chillers SW Isolation Valve 1-Al Note Test Frece Stroke Q
Stroke Q
4664 4670 4733 4734 4735 4780 5171 5871 5872 5873 5874 5875 5876 MOV MOV MOV MOV MOV MOV MOV APV APV-APV APV APV Turbine Building SW Iso-lation Valve 1-A2 Turbine Building SW Supply Isolation Valve 1-Bl Air Cond. Chillers SW Isolation Valve 1-A2 Aux. Build.
SW Isolation Valve 1-B2 Aux. Build.
SW Isolation Valve 1-A2 Condenser Circulation Pump Seal Isolation Valve Turbine Build. Fire Water Loop Supply Isolation Valve Cont:ainment Post Accident, Filter Damper Containment Post Accident Filter Damper Containment Post Accident Filter Damper Containment Post Accident Filter Damper Containment Post; Accident Filter. Damper Containment Post Accident Filt:er Dam er Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
St:roke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
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QUALITY ASSURANCE MANUAL GINNA STATION TITLE APPENDIX C
, Ginna Station Inservice',Pump'nd Valve Testing Pxogram for the September 1
1977 Thxough May 31, i979 Period PAGE 17 OF 23 DATE Sept.
1, 1977 4.9 Category C Check Valves Valve N
~Te 710A 710B Descri tion Check Discharge 1-A RHR Pump Check Discharge 1-B RHR Pump Note Test F~xe Stroke Q
Stroke Q
72 3A 842A 842B 847A 847B CV CV CV Discharge Check Valve 1-A CC P.ump First. Check Valve in Loop A Accumulator Dump Line First, Check Valve.in Loop B Accumulator Dump Line A-CSP From Spray Additive Tank to Eductox B-CSP From'Spray Additive Tank to Eductor Stxoke Q
Stroke Q
Stroke Q
Stroke Q
Stroke Q
853A 853B 854 CV Core Deluge Check CV Core Deluge Check CV RHST to RHR Pump Check 10 Stroke'/R 10 Stroke C/R 11 Stroke C/R sees 866B 867A 867B 878G CV CV CS Pump 1-A to Charcoal Filter Deluge CS Pump 1-B to Charcoal Filter Deluge Accumulator Dump and SI to Cold Leg Loop B Accumulator Dump and SI to Cold Leg Loop A 1-A SI Pump to Cold Leg LoopB After MOV 878B 12 13 Stroke C/R 13 Stroke C/R 13 Stroke C/R
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QUALITYASSURANCE MANUAL GINNA STATION TITI.E APPENDIX C Ginna Station Inservice Pump and Valve Testing Program for the September 1,
1977 Thxough May 31, 1979 Period DATE 49 90C Sept.
1, 1977 PAGE 18 DP 23 878J CV 1812A CV Valve N
~Te 1-B SI Pump to Cold Leg Loop A After MOV 878D 1-A RCDT Pump to 1-B RHR HX Note Test F~re 13 Stroke C/R Stroke Q
1812B CV 1B RCDT Pump to 1A RHR HX Stroke 3516 3517 CV 1B S/G Main Steam Swing Check Stop Valve 1A S/G Main Steam Swing Check Stop Valve
'14 Stroke 14 Stroke Start-up Start-up 3998
.4003 4004 4009 4010 4014 4016 4017 CV AFP Discharge Check Valve CV CV CV 1A MDAFP to S/G 1A Check Valve 1B MDAFP to S/G 1B Check Valve TDAFP Condensate Suction Check Valve I
CV 1B MDAFP Suction Check CV 1A MDAFP Suction Check Valve CV TDAFP to S/G lA Check Valve CV TDAFP to S/G 1B Check Valve Stroke Stroke Stroke Stroke Stroke Q
Stroke Q
Stroke Q
Stroke Q
4023 CV TDAFP Recirculation Check-Valve Stroke 5133 CV 'iesel Pump Disch. Check Valve Stroke Q
5136 CV Motor Pump Discharge C.V.
Stroke Q
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QUALITYASSURANCE MANUAL GINNA STATION TITLE APPENDIX C Ginna Station Inservice'Pump and Valve Testing Program for the September 1, 1977 Through Ma 31 1979 Period 19 oF 23 DATE Sept..
1, 1977 PAGE 4.10 Category C Relief Valve Valve N
~Te Note Test F~xe 203 209 434 435 732 755A 755B RV Letdown High Pressure Safety Relief RV Letdown Low Pressure Safety Relief RV Pressurizer Relief RV Pressurizer Relief RV CC Surge Tank Relief RV CC Prom A RCP Thermal Barrier Relief RV CC Prom B RCP Thermal Thezmal Barrier Relief 15 15 15 15 15 861 RV 1-B CS Pump Suction Relief 15 887 1817 3508 3509 3510 3511 3512 RV On SI Test Line Inside Containment RV Alternate Suction Prom RHR Pump to C SI Pump RV 1-B S/G PRV RV 1-A S/G PRV RV 1-B S/G PRV RV 1-A S/G PRV RV 1-A S/G PRV 15 15 15 15 15
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QUALITY ASS0RANCE MANUAL GINNA STATION APPENDIX C Ginna Station Inservice Pump and Valve
- , Testing Program for the September, 1~ 1977 Through Ma 31,'979 Period DATE 40 90C 20
~
oF 23 Sept.
1, 1977 PAGE Valve 5
~Te Descri tion Note Test F~re 3513 RV 1-A S/G PRV 15 3514 3515 5134 5135 RV 1-B S/G PRV RV 1-A S/G PRV RV Diesel Pump Disch R.V.
RV Motor Pump Disch R.V.
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'Insezvice Valve Testing Notes 15 15 15 15 Note 1 Valves
- 304A, 304B and 313 cannot be stroked during normal plant operation on a quarterly basis because they would interrupt coolant flow to the reactor coolant pump seals.'hese valves will be stroked at cold shutdowns or re-fueling outages.
Note 2
Valve 370B cannot be stroked during normal plant operation on a quarterly basis because this test. would interrupt charging pump flow.
This valve will be stroked at cold shutdowns or refueling outages.
Note 3 Valves 371 and 427 cannot be stroked dur-ing normal plant operation on a quarterly basis because this test would interrupt the letdown (CVCS) system.
These valves will be stroked at cold shutdowns or refueling outages.
Note 4
Valve 383B cannot be stroked during normal plant operation on a quarterly.-
basis because this test would result in substantial radiation exposure to test
~
personnel.
A recent survey in the area of the test connection indicated a
neutron field of 500 mr/hr and a gamma field of 250 mr/hr.
This valve will be
- stroked, at. cold shutdowns or refueling outages.
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QUALLTY'ASSURANCE MANUAL GINNA STATION TITLE APPENDIX C Ginna Station Inservice Pump and Valve Testing Program for the September 3.,
1977 Through Ma 31 1979 Period DATE Sept.
1, 1977 PAGE 21 D"
23 Note 5Valves 750A,
- 750B, 759A and 759B cannot be stroked during normal plant operation on a quarterly basis because this test would require the reactor coolant pumps to be shut down to eliminate the flow thxough these checks and NOVs.
These valves will be stroked at cold shutdowns or refueling outages.
Note 6 Note 7 Valves 813 and 814 cannot be stroked dur-ing normal plant operation on a quarterly basis because this test would remove the coolant to the reactor vessel supports and cavity wall.
These valves will be stroked at cold shutdowns or refueling outages.'alve 879 is a manual valve in the safety injection test line and is kept locked shut.
This valve is not required to change position to perform a safety func-tion.
The only requirement, is that leak-age through valve 879 be acceptably low.
Therefore, the quarterly stroke test has been deleted.
This valve will be leak tested at refueling outages.
Note 8Valves 700 and 721 cannot be stroked dur-ing normal plant operation on a quarterly basis because there is an interlock sys-tem which prevents these valves from opening when the primary system is at operating pressure.
Valves 700,
- 701, 720 and 721 separate a high pressure system from a low pressure system.
These valves will be stroked at cold shutdowns or refueling outages.
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QUALITYASSURANCE MANUAL GINNA STATION TITLE APPENDIX C Ginna Station Inservice Pump and Valve Testing Program for'the September l~ 1977 Through Ma 31, f979 Period 22 oF 23 OATE Sept.
1, 1977 PAGE Note 9
Valves
- 825A, 825B,
- 856, 896A, and 896B should not be stroked during normal opera-tion on a quarterly basis because this would cause a temporary loss of system function of the ECCS.
These valves pro-vide the suction from the refueling water storage tank to the safety injection and residual heat removal pumps.
These valves will be stroked at cold shutdowns or re-fueling outages.
Note 10- Valves 853A and 853B cannot be stroked dur-ing normal plant operation on a quarterly basis because this test would pressurize the RHR system to the primary system opera-tion pressure.
These valves will be stroked at cold shutdowns or refueling outages.
Note ll-Valve 854 cannot be stroked during normal plant operation on a quarterly basis be-cause there is not a way to establish a
flow through this valve when the primary system is at pressuze-and the RHR system is not operating.
This valve will be stroked at cold shutdowns or refueling outages.
Note 12-Valves 866A and 866B cannot be stroked at any time because they are part of the con-tainment spray system, which when pressurized, sprays borated water and/or sodium hydroxide solution throughout con-tainment.
Such a condition would be in-tolerable for future plant operation.
An air test could be performed by supplying a large volume of air to the spray ring header which hopefully would be able to liftthe check valve flapper.
At this time there is not any instrumentation to verify check valve operability, even if an air test would liftthe flapper.
Therefore, this valve will not be tested until a proper modification may be made in the future.
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QUAblTY AS)URANCE MANUAL GINNA STATION APPENDIX C Ginna Station Inservice Pump and Valve Testing Program for the September 1,. 1977 Through Ma 31 1979 Period DATE Sept.
1, 1977 PAGE 23 oF 23 Note 13-Valves 867A,
- 867B, 878G, and 878J cannot be stroked during normal operation on a quarterly basis because this test cannot be done when the primary system is at operating pressure.
This test may only be done when the plant is in a cold shutdown condition with a partially full primary system in order to prevent an overpressurization.
Note 14-Valves 3516 and 3517 cannot.
be stroked during normal plant operation in a quarterly basis because they are the main steam swing check stop valves.
These valves are stroked during each plant startup.
Note 15-Category C Relief Valves shall be tested in accordance with the extent and frequency requirements of Paragraph IWV-3510 of Article IWV of Section XI of the Code.
PVT 5.0 Records 5.1 Records for the Inservice Pump Testing Program shall be developed and maintained in accordance with Article IWP-6000 of Section XI of the Code.
5.2 Records for the Inservice Valve Testing Program shall be developed.
and maintained in accordance with Article IWV-6000 of Section XI of the Code.
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