ML20099C052
| ML20099C052 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 07/29/1992 |
| From: | Link B WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CON-NRC-92-082, CON-NRC-92-82 VPNPD-92-266, NUDOCS 9208030282 | |
| Download: ML20099C052 (5) | |
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!Electnc POWER COMPANY 2r w mengan. 90 so. ?c4o '.wo+en w M2m ut4)22$ 2345 VPNPD-92-266 NRC-92-082 July 29, 1992 Document Control Desk l
U.
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NUCLEAR REGULATORY COMMISSION Mail Station P1-137 Washington, DC 20655 Gentlemen:
DOCKETS 50-26s_AND 50-301 PUMP AND VALE IN-SERVICE TEST PROGRAM VALVE RELIEF REOUESTS/ COLD SHUTDOWN JUSTIFICATIONS 1
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 i'
Enclosed are two requested revisions to our Pump and Valve In-Service Test (IST) Program.
The first requested revision, Valva Relief Regaest VRR-35, " Main Steam and Reactor Coolant Safety Valves," will permit main steam safety valves and pressurizer safety valves to be returned to service without having their valve set pressures retested following
" Jack and Lap" procedures.
These maintenance procedurva involve the removal of 0.002 inch or less of seating material and have a predictable effect on the set pressure of the subject safety valve.
j Ir all cases, the valves will be returned to service with their valve set pressures within the tolerance specified by ASME/ ANSI i
OM-1-1981, " Requirements for Ir-Service Performance Testing of Nuclear Pcwer Plant Pressure Relief Devices."
- Hence, j
verify the valve set pressure is not required.
' retesting to We are aware of the prablems encountered by Duke Power Company when using " Jack and Lap" procedures on their pressurizer safety valves,
{
i manufactured by Dresser Industries, as discussed in NRC Information l
Notice 91-74, " Changes in Pressurizer Safety Valve Setpoints Before l
Installation."
We believe, however, that our main steam and j
pressurizer safety valves, manufactured by Crosby Valve and Gauge
]
Company, are sufficiently different in design that they will not experience similar problems.
As stated in enclosed VRR-35, we have received information from j
Crosby Valve and Gauge Company whit:h specifies the calculated l
changes in valve set pressure followina a " Jack and Lap" procedure i
in which not more than 0.092 inch of material is removed from the I
valve seating surface.
Subsequent discussions with Crosby valve l
and Gauge Company representatives confirm that they have test data f
I which support these c Jculated channes in valve set pressure.
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Document Control Desk July 29, 1992 i
Page 2 i
i The second requested revision, Cold Shutdown Justification CSJ-34, acharging Pump suction Valves," is required in order to avoid undesired and potentially serious plant transients.during testing of certain charging pump suction valves.
11e look forward to receipt of your response concernir.g these revisions to our program.
Should you have any questions or require any additional information, please contact us.
i Sincerely, h
l/l 4
(
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--J Boo Link Vice President 1
Nuclear Power j'
Enclosures Copies to: NRC Resident Inspector NRC Regional Administrator, Region III Adele DjBlasio, Brookhaven National Laboratory 1
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i RELIEF REQUEST NO. VRP.-35 e
i SYSTEMS:
Main Steam (M-201, Sh 1; M-2201, Sh 1) i Reactor Coolant (541F091, Sh 1 & 2;
- 541F445, Sh 1 & 2) 3 i
COMPONENTS:
MS-02005 (Units 1&2)
MS-02006 (Units 1&2) j MS-02007 (Units 1&2)
MS-02008 (Units 1&2)
MS-02010 (Units 1&2)
MS-02011 (Units 1&2) l MS-02012 (Units 1&2)
MS-02013 (Units 1&2)
RC-00434 (Units 1&2)
RC-00435 (Units 1&2) 4 CATEGORY:
C l
l FUNCTION:
i Main ste,: safety valves provide steam generator over iressure protection and an additional heat sink for core cooling.
Pressurizer safety valves provide over-pressure protection for i
l l
BECTION XI_BEQJJIREMENT:
i For safety valves, corrective action and additional testing shall be in accordance with the requirements of ASME/ ANSI OM-1-1981, for valves not meeting acceptance criteria of ASME/ ANSI 4
j OM-1-1981.
(IWV-3513) i For safety valves, refurbished equipment shall be subjected to tests performed in the following sequence:
(a) visual examinatior.-
l (b) seat tightness determination (c) set pressure determination (d) determination of compliance with the Owner's seat tightness criteria i
(e) determination of electrical cha;acteristics and l
operation of bellows alarm switch-c
-(f) verification of the integrity of ba]cncing devices on l
balanced va'_ves (g) determination of operation and electrical l
cnaracteristics of position indicators
)
(ASME/ ANSI OM-1-1981, 7. 3.1.1 and 7. 4.1.1) i l
DASIS FOR 3ELIEF:
Experience has shown nat, for the valves in question, there exists an absolute r ximum change in relief set pressure following a " Jack and Lap" procedure where not more than 0.002 l
inch of seating material is removed.
Transmittals from Crosby t
I
Velve and Gage Company show the calculated naximum change in valve set pressure resulting from a'0.002 inch " Jack and Lap" is 2.3 psig (0.2%) for main steam safety valves, and 9.0 psig (0.36%) for pressurizer safety valves.
Subsequent telephone conversations with Crosby Valve and Gage Company Engineering (Crosby) confirmed that Crosby has performed actual tests to substantiate their calculations.
The percentage change in nameplate set pressure in each case is well below the 3% change acceptance criteria called out in ASME/ ANSI OM-1-1981, 1.3.3.4.
9 Thus, the change in set pressure due to the " Jack and Lap" is within the tolerance specified by ASME/ ANSI OM-1-1981.
ALTERNATE TESTING:
Following " Jack and Lap" procedures on either a main steam safety valvn or pressurizer safety valve in which the maximum total amount of seating material removed is not more than 0.002 inch, t.o set pressure test will be performed prior to returning the valve to service provided:
ij The calculated raximum chenge in set pressure is applied to the valve set pressure obtained prior to the " Jack and Lap" procedures.
This is 0.2% for Main Steam Safety Valves and 0.."
for Pressurizer Safety Valves.
- 2) The newly calculated valve set pressure is within the 3%
tolerance of valve nameplate set pressure called out in ASME/ ANSI OM-1-1981.
If the above conditions are not met, the valve will have its set pressure tested prior to return to service as specified in ASME/ ANSI OM-1-1981, 7.3.1.1.
In every case, all testing other than the set pressure deter-mination will be performed as required in ASME/ ANSI OM-1-1981.
5 STATUS:
Submitted to tne NRC for review and approval July 1992.
s 1
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COLD SHUTDOWN JUSTIFICATION CSJ-34 CV-112B (Units 1&2) Charging Pump Suction MOV From the-RWST CV-357 (Units 1&2) Charging Pump Suction Check Valve from the RWST Exercising tne3e valves to the open position during plant operation would result in the injection of a2000 ppm borated water from the refueling water storage tank (RWST) to the reactor coolant system (RCS).
This would result in an undesirable reactivity trarsient leading to a temperature transient-with:the potential for a plant trip and safety. injection'.
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