ML20043H934
| ML20043H934 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 06/14/1990 |
| From: | Sieber J DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20043H935 | List: |
| References | |
| GL-89-04, GL-89-4, NUDOCS 9006270099 | |
| Download: ML20043H934 (13) | |
Text
....
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gvaje her smun SNppinggxyt PA 18.2077 0004 P.,
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June 14, 1990 U.
S.
Nuclear Regulatory Commission Attn:
Document Control Desk Washington, DC 20555
Reference:
Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Updated Inservice Testing (IST) Program Gentlemen:
The purpose of this submittal is to provide the NRC wii.h an informational copy of revisions to the Beaver Valley Unit No. ! IST Program.
On October 3,
- 1989, in response to Generic Letter 89- 04, we submitted revision 4 of the Unit No. 2 IST Program.
Included as part of revision 4
were certain relief requests requiring NRC approval prior to our implementation.
In an effort to better implement our program revisions, we have reissued revision 4 with the following changes:
1.
Removed those relief requests requiring prior NRC approval
- and, 2.
Added certain program changes permitted by ASME XI and Generic Letter 89-04 Included with this submittal is Enclosure 1 which contains those relief requests requiring prior NRC approval which were part of our October 3,
1989 submittal.
We have labeled this section as Proposed Revision 2A.
Upon NRC approval of these relief requests, they will be formally issued as an additional revision to the Unit No. 2 IST Program.
Also included as Enclosure 2
is the current implemented Unit No.
2 IST Program.
The current program consists of a new revision 4 as stated earlier and partial revisions (numbers 5 and 6).
Enclosure 2
represents the complete program with revisions 5 and 6 integrated into the reissued revision 4.
It is being provided for information to the NRC as the current program of record.
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,BOOv0r Volloy Powar Station, Unit No. 2 Docket No. 50-412, License No. NPF-73
'Page 2 Each enclosure also contains attachments describing-changes-associated -with each-revision.
Future changes to the IST program
.will bec handled in this manner.
Changes to the Unit No. 2 program
' requiring prior NRC approval will be labeled " Proposed Revision 2_"
lettered sequentially according to the last revision formally reviewed by the NRC.
Actual program changes which are implemented will be issued' to the NRC for information, including approved.
proposed revisions.
If you have any questions, please contact me or members of my staff.
Sincerely hir ice President Nuclear Group cc:
Mr. J.
Beall, Sr. Resident Inspector Mr. T. T. Mortin, NRC Region I Administrator Mr. A. DeAgazio, Project Manager Mr. R. Saunders.(VEPCO) w/o enclosures
i, ENCLOSURE 1 Contents;
~
Beaver Valley Unit No. 2 Inservice Testing Program; Proposed
' Revision 2A;(Revisions requiring NRC approval).
. Attachment 1;
Summary of Changes included in. Proposed'
. Revision 2A.
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RAPID ACTING VALVES n
2RCS*SOV200A 2LMS*S0V950
~2 MSS *S0V105EJ
~2RCS*SOV200B 2LMS*SOV951-12 MSS *S0V105F.
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12RCS*SOV201A-2LMS*S0V952
~ 211CS*SOV114 A-'
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-2RCS*SOV201B 12LMS*S0V953 2HCS*S0V114B.
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'2RCS*PCV4550
- 2QSS*S0V100A
-211CS*SOV115AL 2RCS*PCV455D.
- 2QSS*SOV100B 211CS*SOV115B 2RCS*PCV456 2QSS*SOV101A' 2HCS*SOV133A' 4
'2CHS*SOV206 2QSS*SOV101B-2HCS*SOV133B~
2GNS*S0V853A 2QSS*SOV102A 211CS*SOV134A' S
1lv "
2GNS*SOV853B' 2QSS*SOV102B-2HCS*SOV134B 2GNS*SOV8530.
2SSR*A0V112A-2 211CS*S0V135 A 2GNS*SOV853D-
.2SSR*S0V128A-1 2HCS*SOV135B
.2GNS*S0V853E 2SSR*S0V128A-2 2HCS*SOV136A' 2GNS*SOV853F.
2SSR*SOV129A-1 2HCS*SOV136B, 2GNS*SOV854A
'2SSR*S0V129A-2 L2GNS*SOV854B 2SSR*SOV130A 1 2CVS*S0V102 2SSR*SOV130A 2CVS*SOV151A=
2 PAS *SOV105A-1 f.
--2CVS*SOV151B 2 PAS *SOV105A-2 2CVS*SOV152A-2CVS*S0V152Bi 2CVS*SOV153A
'4 2CVS*SOV153B1 o
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I i-U 182 ISSUE 1 REV 4 04 T
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t ATTACHMENT 1 LIST OF CHANGES REMOVED FROM REVISION 4 AND SEPARATED INTO PROPOSED REVISION 26 The following changes were identified to the NRC in the original' Revision 4-of the Unit 2 IST Program as requiring NRC approval prior to implementation.
These changes are now being considered as " Proposed Revision 2A" to the Unit 2 IST Program. While NRC review and approval of Proposed Revision 2A is in-progress, a " revised" Revision 4,
which includes all remaining Revision 4-changes and,some additional changes not requiring prior NRC. review and approval, can now be implemented. The " revised" Revision 4 has deleted any reference to the following changes and has returned the affected portions of the IST Program back to original status.
- 1) Changed the Pump Testing Outline Sheets for the Chemical Injection Pumps
[2QSS*P24A and B)
(pages 19 and 20) back to original status since the change 'previously submitted to the NRC as Pump Relief Request No. 8 in the original Revision 4 requires prior NRC approval before it can be implemented.
Also deleted Pump Relief Request No. 8 from this revision-
.until it has been approved by the NRC. The necessary changes associated with Pump Relief Request No.
8 will be included in the next available revision to the Unit 2 IST Program upon NRC approval of Proposed Revision 2A.
- 2) Changed the Valve Testing Outline Sheets for the Reactor Vessel Head Vent Valves
[2RCS*SOV200A,B],
[2RCS*SOV201A,B) and [2RCS*HCV250A,B) (page 55) back to original status since the change previously submitted to the NRC as Relief Request No.
33 in the original Revision 4 requires prior NRC approval be fore it can be implemented. -Also reinstated CSJ No. 3 (page 124) and deleted Relief Request No. 33 from this revision until it has
.i been approved by the NRC. The necessary changes associated with Relief Request No. 33 will be included in the next available revision to the Unit 3
2 IST Program upon NRC approval of Proposed Revision 2A, i
- 3) Deleted the Personnel and Emergency Airlock Valves added to the Unit 2 IST Program in the original Revision 4 on the System 47 Valve Testing Outline Sheet (page 121) since Relief Request No's. 31 and 32 associated with these valves require prior NRC approval before they can be implemented.
Also deleted Relief Request No's. 31 and 32 from this revision until they have been approved by the NRC.
The necessary changes associated with Relief Request No's.
31 and 32 will be included in the next available revision to the Unit 2 IST Program upon NRC approval of Proposed Revision 2A.
PACE 1 0F 7
i LIST OF TECHNICAL CHANGES TO THE UNIT 2 IST PROGRAM (REV.4) r 1)- Pump : Relief. Request No. I was deleted and paragraph two' was added to the
" Pump'= Testing Requirements" Section on page 5 to describe how the-use of a " pump curve" can be used in surveillance testing without the need-for requesting relief from the ASME XI Cod 6
("At certain times plant conditions may preclude returning a pump to the same reference condition for -its normally scheduled surveillance.
Since_IWP 3112 permits the establishment of additional sets of reference values, a pump curve which is merely a graphical representation of these reference values will be used.").
In addition, NRC approved Revisions 0 and 1 to the Unit 2 IST.
Program also used a similar paragraph while not requesting relief for the use of a pump curve for any specific surveillance of pumps.
- 2) Pump Relief Request No. 2 was deleted because it was discovered that it was not applicable.
Pump Relief Request No. 2 requested relief from the
.ASME XI Code because it was thought the thermocouples and Plant computer used to measure ~ pump and motor bearing temperatures exceeded the range requirements of IWP 4120 (The full scale range of each instrument shall be three times the reference value or less.).
Further investi ation 6
found that the thermocouples used in conjunction with the Plant computer do meet the range requirements of IWV 4120.
The type T thermocouples supplying signals to. the -computer points have a standard accuracy of
+/ 1.~8F over a range of -328 to +662F (
Reference:
Omega Complete Temperature Measurement Handbook -and Encyclopedia, Vol. 26, Table H.
Page' T 37).
The range of the computer points used are only 0 250F, and bearing temperatures are typically in the range of 100-180F,
- 3) The following Relief Valves were added to the IST Program following an
-extensive valve comparison review between the Unit 1 and Unit 2 IST Programs. They will be tested by 2BVT 1.60.5 at refuelings:
(2CHS*RV260A,B,C)
Reactor Coolant Pump Seal Water Penetration Relief Valves (page 59)
[2 SIS *RV858A,B,C)
Accumulator Relief Valves (page 70)
[2 SIS *RV8864A,B]
LHSI Pump Discharge Relief Valves (page 73)
(2 SIS *RV8865)
LHSI Pumps Combined Hot Leg Injection Relief Valves (page 73)
(2ECA*RV205,206, Diesel Generator Air Receiver Relief Valves 207,208]
(pages 114 and 115)
- 4) Added CSJ No.
54 (page 151) for Component Cooling Discharge Header Cross Connect Manual Isolation Valves [2CCP*27A,27B]
(page 86) and
[2CCP*354,355)
(page-90) to permit stroke testing of these valves at Cold Shutdown per OST 2.1.10.
The manual valves can no longer be tested quarterly during the Component Cooling Pump tests as explained in the
)
CSJ.
These. changes were previously reviewed and approved by,the OSC, ORC, and General Manager Nuclear Operations on 9/1/89.
PACE 2 0F 7 i
LIST OF TECHNICAL CRANGES TO THE UNIT 2 IST PROGRAM (REV.4) (Cont'd) s
- 5) The Main -Feed Reg Valves [2FWS*FCV478,488,498) (page 97) were added to-y the IST Program per ISEC Letter NDISEG:0354, dated October 3, 1989, and will be tested at Cold Shutdown per OST 2.1.10.
CSJ No. 55 (page 152) was added to permit testing these valves at Cold Shutdown.
- 6) The 'Hain Feed Bypass Valves [2FWS*FCV479,489,499) (page 97) were added to the IST Program per ISEG Letter NDISEG:0354, dated October 3,'1989, and will be-tested at Cold Shutdown per OST 2.1.10.
CSJ No. 56 (page 152) was added to permit testing these valves at Cold Shutdown.
- 7) Reverse direction testing of the Auxiliary Feedwater Check Valves
[ 2 FWE*99,100,101) is also performed by_ monitoring upstream. pipe
+
temperatures: at least quarterly per OM 54, Log L3 26.
This testing was added to the Comments column for thear valves on pages 98 and 99, and to-Relief Request-No, 19 (page 166) as :
itional alternate testing.
This addition meets the requirements of Cer a ac Letter No. 89-04
- 8) On page 106, the Main. Steam Valve Area Cooler Flow Control' Valves'
[2SWS*FCV120A,B) were changed from " active" to " passive" valves because their NSA position was changed from Automatic to Open. These valves fail open during an accident and are now already open.
- 9) Containment Mose Rack Header Isolation. Valves' [2FPW*A0V206) and-
[2FPW*761)
(page 111) were added to Relief Request No. 2 (page~156) to, take exception to IL'V 3427(b) as permitted by Generic Letter No. 89 04-for valves 6 inches in diameter or larger.
10) 2BVT 2.47.2 was added as a special test to Relief Request No. 1 (page 154) as additional alternate testing when a Type C leak test is required for any relief valves which have had maintenance performed on them.
- 11) OST 2.11.15 was added as a special test to Relief Request No. 10 (page 161) as additional alternate testing when a partial forward stroke-exercise is required for any SI Accumulator Discharge Check Valves'which have had' maintenance performed on them.
These changes were previously reviewed and approved by the OSC, ORC, and General Manager Nuclear Operations on 9/1/89.
PAGE 3 0F 7 L
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4 g' LIST OF EDITORI AL CHANCES TO THE UNIT 2 IST PROCPM (REV.4) i
- 1) A " List of Effective Pages" (pages 1 111) was added to the front of the i
Unit 2 IST Program.
tracking. future revisions where only j
to aid in partial program changes-are incorporated.
~2)
Under the " Pump Testing Requirements" Section:
basis for the IST Program, a) Paragra h one on page 3 added as a r
Generic Letter No.
89 04,
Guidance on Developing Acceptable Inservice Testing Programs."
b) On page 4, the guidance for determining if corrective cetion should be taken was broadened to include an evaluation of the pump's
~;
condition. with respect to system operability and Technical i
Specifications in a manner similar to that in the Valve Testing Requirements Section, c) On page 6 under Item No. 2, deleted "(M)
Monthly Test Frcquency" since it is no. longer referenced on any of the " Pump Testin6 Outline" Sheets, and renumbered the remaining defined frequencies.
l
- 2) On the " Pump Testing Outline" Sheets:
a) With-the deletion of Pump Relief Request No's. 1 and 2, all Pump Relief Requests were renumbered and the Pump Testing Outline Sheets reference.to relief request numbers were revised accordingly.
b) On pages 21-24 for the Recire Spray Pumps, reference to the sump l
1evel mark number was deleted from the comments column under suction pressure (Pi) since (2RSS*L1151A(B)} will no longer be used.
Sump j
level will be measured using a 6 foot rule instead because the level j
indicator only measures in 9 inch intervals.
j c) On pages 25-27 for the Component Cooling Pumps, added an additional Supply Header Flow Indicator to the comments column under flow (Q).
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.d) on pages 28 30, changed the OST (frequency) for the Auxiliary
'l Feedwater Pumps from
"(M)"
to "(Q)", and revised the " Remarks" to j
- read,
" Pump is normally tested monthly." ASME XI only requires a
)
quarterly test frequency, but these pumps are normally tested monthly per Tech Specs as noted in the " Remarks".
- 3) Under the " Valve Testing Requirements" Section:
l a) Paragraph one on page 46 added as a basis for the IST Program, Generic Letter No.
89 04,
" Guidance on Developing Acceptable Inservice Testing Programs."
These changes were previously reviewed and approved by the OSC, ORC, and
]
Ceneral Manager Nuclear Operations on 9/1/89.
{
PAGE 4 0F 7 i
[
a
LIST OF EDITORIAL CHANGES TO THE UNIT 2 IST PROGRAM (REV.4) (Cont'd)
- 3) b) The third paragraph-on page 47 was reinserted _back into the IST Program. following deletion from' the IST Program in Revision 3A i
because _it-explains' how valves with fail safe actuators (ie., air operated valveo) are tested, c) On page-52 under Item No.
.3, deleted "ADC Administrative 1y Controlled (ie,
- locked, sealed)" singe this-abbreviation is no longer used on the Valve Testing Outline Sheets.
i d) On page 52 under Item No. 7 added "SA Semiannually" as another frequency abbreviation.
- 4) For all Valve Testing Outline Sheets (pages 55'120) which-reference OST 2.47.3A in the Comments column, OST 2.47.3B has also been referenced.
OST 2,47.3B will be performed during refueling outages in place of OST 2.47.3A.which is performed quarterly.
- 5) On page 64 for RWST Containment Isolation Valves (2RHS*15) -and (2RHS*107),
the NSA position was changed from ADC S (administrative 1y controlled-shut) to 13 (locked shut).
was' revised to " Stroke, Time, and Fail Closed". each of these valves.
CSJ No. 19 (page 132) was also revised to reflect this
. change.
- 7) On page 65, the Comments column for RHR Hx FCV's [2RHS*HCV758A,B) was revised to " Stroke, Time, and Fail Open" each of these valves.
CSJ No.
21 (page 133) was also revised to reflect this change.
- 8) 2BVT~ 1.11.3, "SI Accumulator Discharge Check Valve Full Stroke Test" was revised to include the testing previously performed by OST 2.11.15,
" Safety Inj ection Accumulator Check Valve. Test."
OST 2.11.15 was deleted from the Comments column for Accumulator Discharge Check Valves (2 SIS *141,
- 142, 145,-
- 147, 148, and 151);on the Valve Testing Outline Sheets. (pages 68 and 69). Relief Request No. 10-(page 161) was also l
l revised to reflect this change under Alternate Test.
- 9) The CMP title referenced at the bottom of page 105.was corrected to read, " CMP 1/2-75 CLOW CHECK 1M".
- 10) One pages 105, 106, and 108, the referenced OST for (2SWS*A0V118A,B],
(2SWS*SOV130A,B),
and (2SWS*697,698) was changed from OST 2.30.17 to-OST 2.30.17A for Train "A" testing and to OST 2.30.17B for Train "B"
testing.
These changes were previously reviewed and approved by the OSC, ORC,.and General Manager Nuclear Operations on 9/1/89.
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PACE 5 0F 7 l
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- 11) The referenced Station Log was changed to Log L4 40 and a description of the-forward flow test for Main Steam Valve Area Cooler Supply Line Check Valves (2SWS*1103 and 1104) was revised to include the location of the area where temperature was being maintained (in the Main Steam Valve Area) on the Valve Testing Outline Sheets (page 108).
- 12) The Comments columns for the following check valves were revised to
- read, "2BVT 1.47.5 FS,RD by leak test (R)".
Their respective relief requests had already been revised in a previous revision to reference a full stroke in the reverse direction (closed) by leak test at refueling.
Valves Pace No.
Relief Reauest No.
(2CVS*93) 75 RR13 (2CCP*289,290,291) 89 RR14 (2CCP*352) 90 RR15 (2 MSS *18,19,20]
92 RR16 (2 MSS *196,199,352) 94 RR16 (2SVS*80,81,82]
96 RR17
[2FWS*28,29,30) 97 RR18 4
(2FWE*99,100,101) 98,99 RR19
[2SWS*1103,1104) 108 RR21
- 13) The referenced Station Logs were changed to Logs L4 29 and L4 32 and a description of the forward flow test for Diesel Cenerator Air Start Compressor Discharge Check Velves (2EGA*100, 101, 130, and 131) was revised-to include more detail on how the check valves are verified to be. opened- (D/C start air header pressure is maintained verifying the check valve is open (IWV-3414)) on the Valve Testing Outline Sheets-(page 114).
- 14) The Basis for CSJ No.
18 was revised to say that a verification of forward. and ' reverse stroking requires pump operation "and non ro*acion of the idle pump respectively." (page 132)
- 15) The Function for CSJ No. 44 was revised by deleting the word " check" from the description of the valves on page 145. These are MOV's not check valves.
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- 16) All Relief Requests associated with Type C testing (RR No's. 1, 23, 24, 25, 26, 27, and 28) were revised in the Alternaes Test and Test Requirements sections to specify "IWV 3427(a)" instead of IWV 3427 in its entirety.
Relief Request No. 2 already encompasses IVV-3427(b).
(pages 154, 169, 171, 173, 175, 177, 179)
I 1
These changes were previously reviewed and approved by the OSC, ORC, and General Manager Nuclear Operations on 9/1/89.
j PAGE 6 0F 7 1
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!! R :
LIST OF EDITORIAL CHANCES TO THE UNIT 2 IST PROGRAM (REV.4) (Cont'd)
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- ~17). The-Alternate Test sections of Relief Request No's. 13,-14, 15, 16 -17, 18 - 19, and 21 were revised to say, " Full stroked. closed by leak test at refueling per...c."-(pages 163 167)
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- 18). Relief Request No.
30 was revised to include a-list of " Rapid Acting Valves" (pages 181 and 182).
L(;
19)- Corrected a typo (" valve") in Relief Request No. 27 (page 177).
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These changes were previously reviewed and approved by the OSC, ORC, and General Manager Nuclear Operations on 9/1/89.
PAGE 7 0F 7 i-
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b 4
.-List.of Technical Changes to the
~ Unit No. 2 IST Proaram! Revision 5-Revision; 5 has incorporated only two areas of change.which are D,
both in compliance with the 1983 edition through summer 1983 addenda of the ASME XI Code-and the positions delineated in Attachment 1 of E-Generic Letter No. 89-04.
These changes are summarized as follows:
1.
Added Cold Shutdown Justification No.
57 changing the testing -frequency of the Quench Spray Chemical Addition Tank Discharge Isolation to Chemical-Injection Pump Valves
[2QFS*MOV102A and B) from quarterly to cold shutdown.
2.
Deleted wording under
" Alternate Test" in Cold Shutdown Justification No.
4 which is no longer required due to the revised content of the" Valve Testing Requirements" Section made in Revision 3/3A to the BVPS-2 IST Program.
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j List of. Technical changes to the j
' Unit No. 2'IST Procramt Revision 6 i
r Revision 6
involves deletion of the following components as a
. result of Amendment No. 28 to the BVPS-2 Technical. Specifications:
1.
Deleted the Standby Service Water Pumps-(2SWE-P21A,B) from the Unit 2
IST Program.
Tech Spec 4.7.13.1.a. no longer.
l requires testing pursuant to Specification 4.0.5 (ASME XI).:
1 The pumps were also deleted out of pump Relief Request No.'3.
for completeness, i
2.
Deleted the NNS class check valves associated with the Standby Service Water Pumps from the Unit 2 IST program.
These included the Pump Discharge Check Valves (2SWE-221,222]
H and the: Vacuum Break Check Valves (2SWE-277,278). ~
NNS class pumps and-valves are not-required to be included in the IST l
Programs.
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