ML20215B762
| ML20215B762 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna, 05000000 |
| Issue date: | 06/12/1987 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 87-184, GL-87-06, GL-87-6, NUDOCS 8706170441 | |
| Download: ML20215B762 (7) | |
Text
i-;'
VIRGINIA ELECTRIC AND POWER CO)!PANY Rxcnwoxu,VINGINIA 20261 June 12, 1987 i
. y g 33, Varm Paumsonut i
Na>cs. man oramarrown United States Nuclear Regulatory Commission Serial No.87-184 Attention: Document Control Desk N0/TAH:jmj Washington, D.C.
20555 Docket Nos.
50-280 50-281 50-338 50-339 License Nos.
DPR-30 DPR-32 NPF-4 NPF-7 Centlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 NORTH ANNA POWER STATION UNITS 1 AND 2-CENERIC LETTER 87-06 PERIODIC VERIFICATION OF LEAK TIGHT INTEGRITY OF PRESSURE ISOLATION VALVES Generic letter 87-06,
" Periodic Verification of Leak Tight Integrity of Pressure Isolation Valves," dated March 13,.1987 requests "a
list of all pressure isolation valves..." for the Reactor Coolant Pressure Boundary (RCPB) and a description of "the periodic tests or other measures performed to assure the integrity of the valve as an independent barrier at the RCPB along with the acceptance criteria.for leakage, if any, operational limits, if any, and frequency of test performance."
i The requested information is provided in Attachment 1 for North Anna Power Station Units 1 and 2 and Attachment 2 for Surry Power Station Units 1 and 2.
North Anna Unit 2 was licensed after 1979 and therefore as indicated in the generic letter, the Unit 2 Technical Specifications includes the appropriate PIVs.
The valves identified for North Anna Unit 1 and Surry Units 1 and 2 are based on the North Anna Unit 2 Technical Specifications list.
Q ADOCK 05000200,"
h'\\
G706170441 870612 PDR P
PDR-
The information contained herein is true and accurate to the best of my knowledge and belief.
Very truly yours,
/YA W. L. Stewart i
Attachments cc:
U. S. Nuclear Regulatory Commission 101 Marietta Street, N.W.
Suite 2900 Atlanta, CA 30323 Mr. J. L. Caldwell NRC Senior Resident Inspector North Anna Power Station Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station
)
I l
I a
I
ATTACHMENT 1-PRESSURE ISOLATION VALVFS LIST AND TESTING CRITERIA 4
l NORTH ANNA POWER STATION UNITS 1 AND 2 l
l i
Virginia Electric and Power Company
4 NORTH ANNA UNIT 1 Valve Number Description Test Type Test Freq.
Accept. Criteria 1-SI-195 Lo Head SI to Leak Test
- C9 Leak Rate <= 1 GPM 1-SI-197 Cold Legs IAW T.S.
or 1-SI-199 4.4.6.2.2 Note 1 1-SI-83 SI to Cold Legs Leak Test
- C9 Leak Rate <= 1 GPM 1-SI-86 (Low and High IAW T.S.
or 1-SI-89 Heads) 4.4.6.2.2 Note 1 MOV-1867C BIT Outlet to Type "C"
- R24 Leak Rate <=.92 MOV-1867D Cold Legs Leak Test SCFH @ 44 psig (Note 3)
MOV-1836 Alt Charging Type "C"
- R24 Leak Rate <=.92 To Cold Legs Leak Test SCFH @ 44 psig (Note 3)
MOV-1890C Lo Head SI to Type "C"
- R24 Leak Rate <=1.8 MOV-1890D Cold Legs Leak Test SCFH @ 44 psig (Note 3) 1-SI-185 Hi Head SI to Type "C" Leak Rate <=.92 1-SI-79 Cold and Hot Leak Test
- P.2 4 SCFH @ 44 psig 1-SI-201 Legs 1-SI-90 1-SI-206 to Head SI to Type "C"
- R24 Leak Rate <=.92 1-SI-207 Hot Legs Leak Test SCFH @ 44 psig MOV-1869A Hi Head SI to Type "C"
- R24 Leak Rate <=.92 MOV-1869B Hot Legs Leak Test SCFH @ 44 psig MOV-1890A.
Lo Head SI to Type "C"
- R24 Leak Rate <=1.8 MOV-1890B Hot Legs Leak Test SCFH @ 44 psig 1-SI-125 Accumulator Periodic
- R24 Leak Rate = 0 GPM 1-SI-127 Discharge Leak Test 1-SI-142 Check Valves 1-SI-144 1-SI-159 1-SI-161 MOV-1700 RHR Supply None Note 2 MOV-1701 Isolation MOV-1720A RHR Return None Note 2 MOV-1720B Isolation
- C9 - Each cold Shutdown but not more often than every 9 months.
- R24 - Each Refueling Outage and at least every 24 months.
Note 1 - >l GPM but <= 5 GPM if the latest measured leak rate has not exceeded the previous leak rate by an amount that reduces the margin between the previous measured rate and the max permissible value (5 GPM) by j
50%.
Note 2 - The integrity of the primary coolant pressure boundary is periodically tested in accordance with Technical Specifications and ASME Section XI hydrostatic test requirements. This testing verifies the integrity of the boundary with the interfacing systems, but not the integrity of each of the individual valves which form the boundary.
Note 3 SI-83,86,89 are tested as PIVs in lieu of these motor operated valves.
1
NORTH ANNA POWER STATION UNIT 2 Generic Letter 87-06 states:
"All plants licensed since 1979 have all PIVs listed in the Technical Specification along with testing intervalo, acceptance criteria and limiting conditions for operation."
North Anna Unit 2 was licensed on April 11, 1980 and therefore, in accordance with Generic Letter 87-06 (page 2 paragraph 1), the requested information is not required.
l i
i
i i
i ATTACHMENT 2~
PRESF3'E ISOLATION VALVES LIST AND TESTING CRITERIA l..
SURRY POWER STATION t-UNITS 1 AND 2 1
l l
j J
l Virginia Electric and Power Company f
l i
l i
t '.3
-j
SURRY UNITS 1 AND 2 Valve Number Description Test Type Test Freq.
Accept. Criteria 1(2)-SI-241 Lo Head SI to Leak Test
- RC9 Leak Rate <= 1 GPM 1(2)-SI-242 Cold Legs IAW T.S.
or 1(2)-SI-243 3.1.c Note 1 1(2)-SI-79 SI to Cold Legs Leak Test
- RC9 Leak Rate <= 1 GPM 1(2)-SI-82 (Low and High IAW T.S.
or 1(2)-SI-85 Head) 3.1.c Note 1 l
MOV-1867C&D Hi Head S1 to Type "C"
- R24 Leak Rate <2.17 l
(MOV-2867C&D) Cold Legs Leak Test SCFH @ 45 psig (Note 3)
MOV-1842 Alt Charging Type "C"
- R24 Leak Rate <.93 (MOV-2842)
To Cold Legs Leak Test SCFH @ 45 psig (Note 3)
MOV-1890C Lo Head SI to Type "C"
- R24 Leak Rate <3.1 (MOV-2890C)
Cold Legs Leak Test SCFH @ 45 psig (Note 3)
MOV-1869A Hi Head Si to Type "C"
- R24 Leak Rate <1.24 j
(MOV-2869A)
Hot Legs Leak Test SCFH @ 45 psig MOV-1869B Hi Head SI to Type "C"
- R24 Leak Rate <.93 (MOV-2869B)
Hot Legs Leak Test SCFH @ 45 psig MOV-1890A&B Lo Head SI to Type "C"
- R24 Leak Rate <3.1 (MOV-2890A&B) Hot Legs Leak Test SCFH @ 45 psig 1(2)-SI-224 Hi Head SI to 1(2)-SI-225 Cold and Hot None 1(2)-SI-226 Legs 1(2)-SI-227 1(2)-SI-228 Lo Head SI to None 1(2)-SI-229 Hot Legs 1(2)-SI-107 Accumulator 1(2)-SI-109 Discharge None Note 2 1(2)-SI-128 Check Valves 1(2)-SI-130 1(2)-SI-145 1(2)-SI-147 MOV-1700&l701 RHR Supply None Note 2 (MOV-2700&2701) Isolation MOV-1720A&B RHR Return None Note 2 (MOV-2720A&B)
Isolation i
- R24 - Each Refueling Outage not to exceed 24 months.
j
- RC9 - Each Refueling or Cold Shutdown after 9 months from last test, or following maintenance.
i I
Note 1 - >l GPM but <= 5 GPM if the latest measured leak rate has not exceeded the previous leak rate by an amount that reduces the margin between the previous measured rate and the max. permissible value (5 GPM) by 50%.
Note 2 - The integrity of the primary coolant pressure boundary is periodically tested in accordance with Technical Specifications and ASME Section XI hydrostatic test requirements. This testing verifies the integrity of the boundary with l
I the interfacing systems, but not the integrity of each of the individual valves which form the boundary.
Note 3 - 1(2)-SI-79,82,85 are tested as PIVs in lieu of these motor operated valves.