ML20085L011
| ML20085L011 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 06/15/1995 |
| From: | George Thomas DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20085L014 | List: |
| References | |
| NUDOCS 9506280234 | |
| Download: ML20085L011 (9) | |
Text
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Beaver Valley Power Station
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(412) 643-8069 FAX GEORGE S. THOMAS N$Ea"NrvI.'." "'
June 15, 1995 Nuclear Power Dwision U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
Subject:
Beaver Valley Power Station, Unit No.1 Docket No. 50-334, License No. DPR-66 Updated Inservice Testing Program, Issue 2, Revision 12 and 12a The purpose of this submittal is to provide the Nuclear Regulatory Commission (NRC) with an informational copy of revisions to the Beaver Valley Power Station Unit 1 (BVPS-1) Inservice Testing (IST) Program. provides a summary of the IST program changes which have been incorporated into Issue 2, Revision 12 and Ih is Issue 2, Revision 12 and 12a of the BVPS-1 IST Program. Included are changes implemented as a result of NRC approval of proposed relief requests.
Additionally, it has been determined that the remaining IST program changes do not require NRC approval prior to implementation. This determination was made because e" c^the changes are either:
in accordance with 10 CFR 50.55a(f), or e
editorial in nature, or e
in compliance with the 1983 Edition through Summer 1983 Addenda of the e
ASME Boiler and Pressure Vessel Code,Section XI, or in compliance with the positions delineated in Attachment 1 of Generic Letter e
No. 89-04, " Guidance on Developing Acceptable Inservice Testing Programs."
2700d3 9506280234 950615 DR ADOCK 05000334 y'g PDR
l Beaver Valley Power Station, Unit No.1 Updated Inservice Testing Program, Issue 2, Revision 12 and 12a Page 2 If you have any - questions regarding this submittal, please contact Mr. Nelson R. Tonet, Manager, Nuclear Safety Depanment at (412) 393-5210.
1, Sincerely,
- f M
George S. Thomas c:
Mr. L. W. Rossbach, Sr. Resident Inspector Mr. T. T. Martin, NRC Region I Administrator Mr. D. S. Brinkman, Sr. Project Manager e
j i-
ENCLOSURE 1
BEAVER VALLEY UNIT 1 IST PROGRAM
SUMMARY
OF CHANGES Issue 2, Revision 12 and 12a i
1 i
J
l D1 CLOSURE 1
SUMMARY
OF CHANGES 'IO 'IHE UNIT 1 IST PROGRAM (REV.12)
I) 'Ihe following changes to the Unit 1 IST Pr@tmu irm utporated Proposed Revisions 1E ard 1F, as approved by the NRC in the SERs dated September 15, 1994, and November 29, 1994, respectively.
A)
Proposed Revision IE revised Pump Relief Request No. 3 of the " Pump Relief Request Section" to allow the use of a portable ultrasonic flow meter to measure the flow for the Boric Acid Transfer Pumps [1CH-P-2A, 2B] during refueling outages.
(page 47 and 48) Also revised the
" Comments" column of the " Pump Outline Sheets" for [1CH-P-2A, 2B] to reference the use of the portable ultrasonic flow meter during the refueling test.
(pages 10 and 11)
B)
Proposed Revision 1F revised the " Pump Testing Requirements Section" and the " Valve Testing Requirements Section" to add a paragraph stating that manufacturer-supplied ASME Code class skid-mounted components are not listed in the IST Pr@tmu but are tested with the parent component.
(pages 4, 61 and 62)
II) The following changes made to the Unit 1 IST Program are in accordance with Regulatory Guide 1.147, Revision 10, July 1993 and Code Case N-465:
A) Revised Pump Relief Request No.1 to include "All of the pumps in the BV-1 IST Pr w tmu."
This revision adds the low Head Safety Injection Pumps
[1SI-P-1A, 1B] and Residual Heat Removal Pumps [1RH-P-1A,1B] to RR1 to obtain vibration readings in velocity units and to delete the requirement to obtain bearing temperatures annually.
(page 45)
B) Revised the " Pump Testing Outline" sheets to reference RR1 for
[1SI-P-1A, 1B] and [1RH-P-1A, 1B].
"Using velocity units" was added to the " Comments" column for vibration readings and the statement that
" Annual bearing terqperature measurement will not be taken since vibration is measured in velocity units" was added to the " Comments" column for bearing temperatures.
(pages 12 - 15)
III)The following changes made to the Unit 1 IST Program are in accordance with the ASME XI Code ard Generic Intter 89-04:
A) Added new Valve Relief Request No. 49 to designate the following valves at BV-1 to be " Rapid Acting Valves":
[SOV-1RC-102A, 102B, 103A, 103B, 104, 105], Reactor Vessel Head Vent
[TV-1CV-102, 102-1], Containment Activity Monitor Discharge Cnmt Isol
[TV-1CV-150A, 150B], Containment Vacuum Pump Cnmt Isol
[TV-1SS-102A1,102A2], RG Cold Ing Sample Header Cnmt Isol
[TV-1SS-105A1,105A2], RCS Hot log Sample Header Cnmt Isol
ENCI.CSURE 1
SUMMARY
OF CHANGES 70 THE UNIT 1 IST PROGFAM (REV.12)
[SOV-1HY-102A1,102A2,102B1,102B2], Hydrogen Analyzer Inlet Sample
[SOV-1HY-103A1,103A2,103B1,103B2], Hydrogen Analyzer Inlet Sample
[SOV-1HY-104A1,104A2,104B1,104B2], Hydrogen Analyzer Sample Disch Per the guidance in G.L. 89-04, this Relief Request is pre-approved.
These valves will have a limitirq stroke time of 2 seconds assigned and the requirement to trend the stroke times will be deleted. (page 200)
Also aMul reference to RR49 on the " Valve Testirs Outline" sheet for the valves listed in the relief request.
(pages 66, 85, 90, 91, 127 -
129)
B) The Reactor Coolant Pump Seal Water Header Isolation, [MOV-1 m -370] and the m argiry Pump Miniflow Header Isolation, [M3V-1 m-373] are normally de-energized open.
They have been reclassified as " passive" and stroking requirements have been deleted frun the " Valve Testing outline" sheet.
The size of [?OV-im-370] was also corrected fran 3/4 inches to 3 inches.
(page 72) RR11 (page 163) for [MOV-1G-370] and CSJ 8 (page 137) for [MOV-1G-373] were also deleted.
C) Revised the valve category to A/P (passive) and deleted the quarterly stroke and time for the Open Pressure Systen Containment Isolation
- Valves,
[TV-1IM-100A1, 100A2]. These valves are currently retired by a temporary modification an:1 will be retired permanently. (page 87)
D) Revised the valve category to A and A/C for the RCP 2hermal Barrier CCR Outlet Isolation Valves,
[TV-1CC-107A, B,
C] and the RCP Thermal Barrier Inlet meck Valves, [1CC-289, 290, 291]. A leak test was also added for the trip valves. The leak test was added as a result of the IST basis review and to be consistent with the BV-2 IST Pmpcuu.
(pages 94, 102)
E) Added CSI 33 for the Air Ejector Air Discharge to Containment meck
- Valve,
[1AS-278] to perform a full-stroke by mechanical exerciser per 10ST-1.10 during Cold Shutdowns.
(page 151)
The " Valve Testing Outline" sheet for [1AS-278] was also revised to add this stroke and reference to the CSJ 33.
10ST-47.3A was corrected to reflect a part-stroke quarterly.
(page 111)
F) Added a reverse direction test, 70P 1-94-10, for the Seal Water to Reactor Plant River Water Pump m eck Valves [1RN-95, 96, 97].
(page 112)
G) Added manual valve [1RN-139), the Control Room AC Condenser Water Booster Pumps [1VS-P-3A, 3B] Suction Cross Connect, to the IST Program.
This valve was added because the NSA of the manual valve will be changed when the internals are placed back into check valves
[1RN-133, 134].
(page 115)
ENCLOSURE 1 ERfRRY OF CHANGES 70 'IHE UNIT 1 IST PROGRAM (REV.12)
H) Changed the valve category of the Recirc Spray Heat Exchanger Header Cross Cunect Valve,
[MOV-1W-104] and the Reactor Plant River Water Supply to Containment Air Recire Coolers / Compressors, [MOV-1 W-116, 117] to B/P (passive) because these valves do not perfonn a function in shutting down the reactor or in mitigating the consequences of an accident.
Also deleted the quarterly stroke of the valves and referenced the Renote Position Verification (RPV) test.
(pages 113 and 115)
I) Revised the valve category to A/C and added a leakage test for the Check valves for Air Supply to the Control Roam Ihmpers, [1VS-544, 545, 546, 547].
(page 125 and 126)
IV) 'Ihe following changes were made to the cupants in the River Water System as a result of design changes. 'Ihe IST changes are either in accordance with ASME XI Code and Generic !.etter 89-04 or are editorial in nature:
A)
Deleted Relief Regaest No. 43 for RP River Water Pump Discharge Check Valves [1W-57, 58, 59] and RP River Water Main Header Check Valves
[1W-106, 107].
'Ihese valves will be full stroked quarterly. Also, revised the " Valve 'Ibsting Outline" sheets to reflect these changes.
(pages 112,114 and 195)
B) Deleted Relief Request No. 44 for River Water Header Isolation Valves to the W side of the RSHXs, [lOV-1W-103A, B, C, D].
These valves will be stroked and timed quarterly. Also, revised the " Valve Testing Outline" sheets to reflect these changes. (pages 113 and 195)
C) Remcned the Recirc Spray Heat Exchanger (RSHX) Supply Header Check
- Valves,
[1W-108, 109] from Relief Request No. 45.
In addition, the statement that quarterly testing through the RSHX will be continued if chamiml treatment is not sucessful was deleted from RR45. Also, revised the " Valve Testing Outline" sheets to reflect these changes.
(pages 114 and 196)
D) Deleted the full stroke quarterly option for the Recirc Spray Heat Exchanger Inlet Check Valves,
[3W -193, 194, 195, 196], per RR45 and revised the OST referenced to 10ST-30.12A (B).
(page 115)
E) Deleted Relief Regaest No.
32 to dimse:nmble and inspect the Diesel Generator Heat Exchanger Inlet Supply Header Check Valves [1W-110,
- 111, 112, 113]
(page 182).
'Ihese check valves have been physically removed from the plant. 'Ihese valves have also been deleted from the BV-1 IST Prupcua. (page 114) _ - - _
DJCIOSURE 1
SUMMARY
OF GANGES 'IO 'IHE UNIT 1 IST PROGPAM (REV.12)
F) Corrected the procedure number that strokes and times the Diesel Generator Heat Exchanger Inlet Supply Header Isolation Valves,
[MOV-1RW-113A, D1] on the " Valve Testing Outline" sheets. 'Ihese valves were realigned and the tests referenced have been revised to reflect i
the correct alignment. (page 114, 115)
V) 'Ihe following changes nade to the Unit 1 IST Program are editorial in
)
nature:
A) Revised the "Punp Testing Requirements" Section to add reference to paragraphs IWP-3210 and 3112, concerning reducing the ASME Range limits for ptrp test quantities.
Also added clarification that vibration readings are obtained per ANSI /ASME OM-6 and that IWP-3210 does not apply to vibrations.
(pages 2 and 3)
B) Revised the drawing number and drawing coordinates for the Quench Spray
- Pumps,
[1QS-P-1A, 1B], the Quench Spray Chemical Injection Pumps,
[1QS-P-4A, 4B, 4C, 4D], the Inside Recirc Spray Pumps, [1RS-P-1A,1B]
and the Outside Recirc Spray Pumps, [1RS-P-2A, 2B]. (pages is - 25)
C)
Corrected the nomenclature for the aincharge pressure indicator for the Quench Spray Pumps,
[1QS-P-1A, 1B] to [PI-1QS-101A, 101B] and deleted the use of the spray line flow indicator, [FI-1QS-104].
(pages 16 -
17) i D) Corrected the comment for flow to reference the PDIs as the primary flow meters used instead of the FIs for Reactor Plant Camponent Cooling Water Pumps, [1CC-P-1A, 1B, 1C].
(pages 26, 27 and 28)
E) Corrected the pump mark numbers listed in Relief Request No. 11 to
[1CC-l'1B and 1C]. (page 55)
F) Revised a portion of the " Valve 'Ibsting Requirements" section concernng Category A valves to state *
"In addition, Category A valves shall be leak rate tested at least once every 2 years, normally, but not tw omarily, at refueling outages.
The Category A valves that are tested in accordance with 10CFR 50, Apperrlix J, Type C (RR1) are leak rate tested normally at refueling cutages, not to exceed every 2 years.
If the leak rate exceeds the allowable 1mit, the valve will be repaired or replaced." (page 60)
A statenent was also added for check valves:
"If the check valves cannot be tested mechanically or with flow, they will be dimncembled and inspected per the requirements o' GL 89-04.
'Ihese valves will normally, but not nmoco rily be inspected during refueling outages."
(page 60)
These statements are editorial in nature in that they merely clarify the requirements of GL 89-04. l
~-
DiCIDSURE 1 f
i
SUMMARY
OF OWJGES 'IO 'IHE UNI 7' 1 IST PROGRAM (REV.12)
G) Deleted the Comnent "Iccked or sealed valve log" fran passive valves:
l
[1CH-25, 26, 27]
(page 68),
[1CH-158,159,161] (page 70), [1SI-41]
i I
(page 79),
[1SI-447, 448, 451, 452]
(page 81), [1PC-9,10, 37, 38]
l (page 103),
[1DA-104,134] (page 121). No testing is required (unless the valves am Category A, and a leak test is required). Deleted test 10ST-24.10 from the Conrnents for passive valves [HCV-1FW-158A, B, C].
(Page 109) i H) Revised RR13 for the Containment Sunp to IHSI Punps Check Valves
[1SI-1, 2]
(page 164), RR25 for the Outside Recirc Spray Punp to HHSI Punp Check Valves [1RS-158,160] (page 175) and RR30 for the Residual Heat Release Check Valves [1MS-80, 81, 82] (page 181) to clarify the frequency of the sanple Mcanaambly per the statement in (F) above.
I) 'Ihe drawing coordinates were corrected for [1SI-451] arri [1SI-452]
(page 81), [MOV-1SI-860B] (page 82), and [}0V-1SI-869A, B] (page 83).
J) 'Ihe drawing numbers and drawing coordinates were corrected for all of the valves in the Quench Spray and Recire Spray systems to reflect the updated drawings.
(page 88 and 89)
K) 'Ihe valve size for the PORV Air SuMly Isolation Check Valves [1IA-116, 117] was corrected after these che.!e valves were modified.
(page 120)
L) Added the refueling frequency test 10ST-47.3B to the " Valve Testing Outline" sheets for the D/G Fuel Oil Pump Suction Cross Connect Valves,
[1FO-116, 117]. (page 123)
M) Corrected the valve type for the SOVs in the Post DBA Hydrogen Control l
system to " Globe" valves.
(page 128 and 129) l N) Revised the Alternate Test of C17 2 for the PORVs to say that
" Full-stroke exercise and timing open will be performed each cold shutdown, not to exceed once rer 92 days... " 'Ihis is to clarify that the Code allowed frequency does apply, as stated in NUREG-1482.
(page 133) l
, t
.- ~
t DK2DSURE 1 SUM 4ARY OF GANGES 'IO 'IHE UNIT 1 IST PROGRAM (REV.12A)
I I) 'Ihe followire charges made to the Unit 1 IST h@tmu are in accordance with the ASME XI Code and Generio letter 89-04, or are editorial in nature:
A)
[1RW-139],
the Control Rocan AC Cbndenser Water Booster Ptmps
[1VS-P-3A, 3B] Suction Cross Cuushet, is being deleted frun the IST l
h-@tmu.
As a result of a design change scheduled to be coupleted during 1R10,
[1RW-139] was aMai to the IST R @tmu in Rev. 12.
However, due to a pr dlem with the design change, [1RW-139] mJst now be deleted frun the IST hwimu.
(page 115)
B)
[1RW-142, 143, 150, 151), the Control Rocan Cooling 0011 [1VS-E-14A, B]
Inlet and Outlet Isolation valves, and [1RW-152, 153] the Control Room AC Cond
[1VS-E-4A, B] Outlet Hdr Isolation valves are being added to the IST Fr@tmu. 'Ihese valves have been tested in accordance with the Code since July 1994, when they were identified for inclusion into the IST Fr@tmu.
(page 115) i I
ENCLOSURE 2 BEAVER VALLEY UNIT 1 IST PROGRAM Issue 2, Revision 12 and 12a