ML20203L485
| ML20203L485 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, 05000000 |
| Issue date: | 08/20/1986 |
| From: | Miosi A COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 2007K, NUDOCS 8608260285 | |
| Download: ML20203L485 (11) | |
Text
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Commonwealth Edison
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One First National Plaza, Chicago, lHinois Address Repy to: Post Omco Box 767
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Chicago, lHinois 60690 - 0767 August 20, 1986 Mr. Harold R. Denton U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, DC. 20555
Subject:
Braidwood Station Unit 1 Preservice/ Inservice Inspection Pump and Valve Program Comparison to Byron Unit 1 Program NRC Docket No. 50-456
References:
(a)
June 20, 1985 A.D. Miosi letter to H.R. Denton (b)
November 16, 1984 T.R. Tramm letter to H.R. Denton
Dear Mr. Denton:
Enclosed is information which will allow you to review the Braidwood Unit 1 Pump and Valve Preservice/ Inservice Inspection Program as compared to Byron Station Unit 1.
The original Braidwood Unit 1 Pump and Valve Program was submitted per reference (a) and Byron's revised program was submitted per reference (b).
The scope of the Braidwood Unit 1 PSI Program is identical to that of Byron Unit 1.
The Braidwood testing program meets the requirements of ASME Code Section XI 1983 Edition.
This is the edition of the Code approved by the NRC for use at Braidwood. 'The approved edition of the Code for Byron Unit 1 was the 1980 Edition, through the Winter, 1981 Addenda.
The PSI /ISI Pump Program for Braidwood Unit 1 consists of a tabular listing of those pumps which are identified in the Braidwood FSAR as Active, and that have an emergency power source.
Also included is a series of notes and relief requests.
Active pumps are defined as those pumps which are called on to perform a safety function as well as to accomplish and maintain a safe reactor shutdown.
The only exception is the diesel driven auxiliary feedwater pump (lAF0lPB) which is included in the program although it is not supplied by an emergency power source.
This pump is included because it is a safeguards feature for the emergency core cooling system (ECCS).
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. Two essential service water makeup pumps (OSX02PA, OSXO2PB) are included in the Byron program.
These pumps supply makeup water for the essential service water cooling towers.
Due to a difference in design. Braidwood does not have these cooling towers, and therefore does not have the pumps.
Therefore the Braidwood program includes two less pumps than the Byron program.
Pump reference values shall be' determined from the results of a preservice test, which may be run during preoperational testing or derived from the first inservice test.
The cross reference listings for the pump program notes and relief requests may be found in Attachments I and II respectively.
The differences between the Braidwood and Byron items are detailed here.
The PSI /ISI Valve Program for Braidwood Unit 1 consists of a tabular listing of Class 1, 2,
and 3 valves which have been assigned a specific Code category and a series of notes and relief requests.
Two CV pump miniflow isolation valves (lCV8114, 1CV8116) are included in the Braidwood program.
These valves will be installed during a Byron Unit 1 outage as part of the centrifugal pump modification package and are not yet a part of the PSI /ISI program.
After installation and prior to service, all valves identified in the Braidwood program willEbe tested as required by Section XI Subsection IWV-3100.
The cross reference listings for the valve program notes and relief requests can be found in Attachments III and IV respectively.
As can be seen from the listings, the items correspond in a one-to-one fashion between Braidwood and Byron.
Please direct any questions you may have regarding this matter to this office.
One signed original and fifteen copies of this letter and enclosure are provided for your review.
Very truly yours, A.
D.
.iosi Nuclear Licensing Administrator
/klj cc:
J.
Stevens enc 1.
2007K 1
Page 1 of 1 Attachment I Braidwood Unit 1/ Byron Unit 1 PSI /ISI Program Plan for Pumps Note Cross Reference List Braidwood Unit 1 Byron Unit 1 Note No.
Note Description Note No.
1 The diesel oil transfer, residual 2
heat removal, and containment spray pumps are lubricated by the fluid pumped and have no indication for lubrication level.
2 Idle inlet pressure cannot be 3
obtained for pumps in continually operating systems.
3 Pump discharge pressure will be used 4
to evaluate the performance of the l
diesel oil transfer pumps.
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Page 1 of 1 Attachment II Braidwood Unit 1/ Byron Unit 1 PSI /ISI Program Plan for Pumps Relief Request Cross Reference List Braidwood Unit 1 Byron Unit 1 Relief Request No.
Relief Request Description Relief Request No.
PR-1 Pump vibration to be measured PR-1 in the more sensitive velocity mode instead of displacement mode.
This relief request includes all the pumps in the program plan (21 for Braidwood and 23 for Byron).
The two essential service water makeup pumps (OSXO2PA,PB) which are at Byron but not at Braidwood represent the difference between the total pumps covered by this relief request.
PR-2 Pump bearing temperatures on PR-2 specified pumps cannot be measured because no permanent temperature detectors / thermal wells are provided.
This relief request includes 13 pumps for Braidwood and 15 pumps for Byron.
As above, the two essential service water makeup pumps (OSX02PA,PB) represent the difference in the totals.
PR-3 Ultrasonic flowmeters will be PR-5 I
utilized to obtain Section XI flow data.
This relief request includes 11 pumps for Braidwood and 13 pumps for Byron.
As above, the two l
essential service water makeup pumps (OSX02PA,PB) represent the difference in the totals.
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Page 1 of 4 Attachment III Braidwood Unit 1/ Byron Unit 1 PSI /ISI Program Plan for Valves Note Cross Reference List Braidwood Unit 1 Byron Unit 1 Note No.
Note Description Note No.
1 The main steam isolation valves 1
(1MS001A-D) will be stroke tested preceding or following cold shutdown per IWV-3412.
Testing of these valves during unit operation would result in a reactor trip.
2 Emergency boration flowpath valves 2
(1CV8104; 1CV8442; 1CV8546; 1CV8804A; ICV 112D,E) will be stroke tested during cold shutdown per IWV-3412.
Testing of these valves during unit operation could result in b' oration of the reactor coolant system.
3 The main feedwater isolation 3
valves (1FWOO9A-D) will be stroke tested during cold shutdown per IWV-3412.
Testing of these valves during unit operation would result in a r
4 The letdown and makeup valves 4
1CV8105; ICV 8106; 1CV8152; l
ICV 8160) will be stroke tested during cold shutdown, per lWV-3412.
Testing of these valves during unit operation i
would result in a reactor l
coolant inventory transient.
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Page 2 of 4 Braidwood Unit 1 Byron Unit 1 Note No.
Note Description Note No.
5 The' valves between the residual 5
heat removal (BHR) pumps and the reactor coolant system (RCS) (lRH8701A,B; 1RH8702A,B) will be stroke tested during cold shutdown, per INV-3522.
Testing of any one valve during unit operation would leave only one valve isolating RHR from the high RCS pressure, which is an undesirable condition.
6 Thirty-seven (37) valves are 6
i identified as intersystem LOCA valves which form a pressure boundary between the RCS and other essential components.
These valves will be leak tested in accordance with the Technical Specifications.
7 The reactor pressure vessel vent 7
valves (lRC014A-D) will be stroke tested during cold shutdown per INV-3412.
Testing of anyone valve during unit operation would leave only one a
i valve as the high pressure boundary, which is an undesirable condition.
8 The residual heat removal pump 8
discharge check valves i
(1RH8730A B) and the centrifugal charging pump discharge check valves i
(lCV8481A,B) will be stroke tested during cold shutdown per IWV-3522.
Testing of these valves during unit operation cannot be done due to high RCS pressure.
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Nineteen (19) check valves will 9
be stroke tested during cold shutdown per IWV-3522.
Testing i
of these valves during unit operation cannot be done due to RCS pressure.
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Page 3 of 4 Braidwood Unit 1 Byron Unit 1 Note No.
Note Description Note No.
10 Feedwater valves (1FWO39A-D) 10 will be stroke tested during cold shutdown per IWV-3412.
Testing of these valves during unit operation would result in termination of the waterhammer prevention feedwater flow.
11 The primary containment purge 11 supply and exhaust valves (lVQ001A,B; IVQ002A,B) will be stroke tested during cold shutdown per INV-3412.
Testing of these valves during unit operation cannot be done because they are the only isolation points between the containment atmosphere and the environment.
12 The auxiliary feedwater check 12 valves (1AF001A.B: 1AF003A,B; 1AF014A-H; 1AF029A,B) will be stroke tested during cold shutdown per Technical Specifications and IWV-3522.
Testing of these valves during unit operation would induce potentially damaging thermal stresses in the upper feedwater nozzle piping.
13 The high head injection isolation 13 valves (1SI8801A,B) will be stroke tested during cold shutdown per IWV-3412.
Testing of these valves during unit operation could result in damaging thermal stresses to the cold leg nozzles as well as a reactivity change.
4 Page 4 of 4 Braidwood Unit 1 Byron Unit 1 Note No.
Note Description Note No.
14 The safety injection system 14 spurious valve actuation group (SVAG) valves will be stroke tested during cold shutdown per INV-3412.
Testing of these valves during unit operation would violate the Technical Specifications.
15 The containment recirculation sump 15 isolation valves (ISI8811A.B) will be stroke tested during cold shutdown per IWV-3412.
Testing of these valves during unit operation would violate the Technical Specifications.
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Page 1 of 3 Attachment IV Braidwood Unit 1/ Byron Unit 1 PSI /ISI Program Plan for Valves Relief Request Cross Reference List Braidwood Unit 1 Byron Unit 1 Relief Request No.
Relief Reauest Description Relief Request No.
VR-1 Primary containment isolation VR-1 valves will be seat leak tested in accordance with 10CFR50, 4
Appendix J in lieu of Section XI requirements.
VR-2 The check valves in the spray VR-2 additive system will be dismantled each refueling outage and full flow tested once every five years.
These valves cannot be stroked without introducing sodium hydroxide into the containment spray (CS) system.
VR-3 The twelve (12) SI check valves VR-3 will be full stroke tested during cold shutdowns provided the reactor vessel head is removed.
Full flow testing during unit operation could lead to an overpressurization of the system.
VR-4 Four (4) CS check valves will be VR-4 partial stroke tested quarterly and full flow tested (or dismantled) each refueling outage.
Full flow testing during unit operation would discharge water through the CS ring headers which is an undesirable condition.
VR-5 The accumulator check valves VR-5 (ISI8956A-D) will be stroke tested during cold shutdown.
Stroke testing during unit operation cannot be done due to the substantial pressure differential between the accumulators and the reactor coolant system.
Page 2 of 3 Braidwood Unit 1 Byron Unit 1 Relief Request No.
Relief Request Description Relief Request No.
VR-6 The SI pump suction check valve VR-6 (1SI8926) will be partially stroke tested periodically and full stroke tested during cold shutdown.
Testing of these valves during unit operation could lead to an over-pressurization of the system.
VR-7 Stroke timing of specified VR-7 solenoid operated valves is impractical due to their fast actuation.
The PS and SX valves will be full stroke tested and fail tested quarterly.
The RC valves will be stroke tested during cold shutdown.
t VR-8 Five (5) component cooling valves VR-8 will be exercised during cold shutdown, provided all of the reactor coolant pumps are not in operation.
Coolant flow is required at all times while the l
pumps are in operation and for an extended period of time l
while in cold shutdown.
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VR-9 These valves (lCV8100, 1CV8112)
VR-9 will be exercised during cold shutdown, provided all of the reactor coolant pumps are not in operation.
These valves cannot be tested during unit operation because seal water flow to the reactor coolant pumps is required at all times during pump operation.
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VR-10 Two (2) instrument air valves VR-10 l
(lIA065, IIA-066) will be exercised during cold shutdown, providing that all necessary equipment required for cold l
shutdown operations would not be affected.
Testing of these valves during plant operation would isolate the air operated instruments / valves in the containment.
Page 3 of 3 Braidwood Unit 1 Byron Unit 1 Relief Request No.
Relief Request Description Relief Request No.
VR-ll Position / Travel indication tests VR-ll will be performed once every three (3) years, or once every 4
other refueling outage.
VR-12 Fast-acting valves will have a VR-12 maximum stroke time limit increase of 100%, with no trending of stroke times required.
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