ML20118B916
| ML20118B916 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 09/28/1992 |
| From: | Chris Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20118B917 | List: |
| References | |
| NUDOCS 9210080110 | |
| Download: ML20118B916 (7) | |
Text
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[gh" "IC g Do UNITED STATES m f,j NUCLEAR REGULATORY COMMISSION t
WASHINGTON. D. C. 20555 49.....,6 PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-353 LIMERICK GENERATING STATION, UNIT 2 A"'nMENT TO FACILITY OPERATING LICENSE Amendment No. 22 License No. NPF-85 1.
The Nuclear Regu) y Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company (the licensee) dated July 7, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and Si) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
921008011o 92o928 PDR ADOCK 0500 3
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2.
Acccrdingly,thelicenseisamendedfbychangestotheTechnical-Specifications as indicated in the attachment to-this license amendment, and paragraph 2.C.(2) of facility Operating License No. NPF-85 is hereby amended to read as follows:
Technical Soecifications The Technical Specifications contained in_ Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 22, are hereby incorporated into this license.
Philadelphia Electric Company shall operate the facility in accordance with the Technical Sp;cifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance and shall be implemented by February 28, 1993.
FOR THE NUCLEAR REGULATORY COMMISSION Y O sY-TS &
Charles L. Miller, Director Project Directorate I-2 Division of Reactor Projscts - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 28, 1992 l
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ATTACHMEN1 TO LICENSE AMENDMENT NO. 22 FACIll1Y OPERATING LICENSE NO. NPF-85 DOCKET NO. 50-353 Replace the following pages of the Appendix A Technical Specifications with the attached page.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Overleaf pages are provided to maintain. document completeness.*
Remove Insert 3/4 6-23 3/4 6-23 3/4 6-24 3/4 6-24*
3/4 6-41 3/4 6-41 3/4 6-42 3/4 6-42*
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1ABLE 3 J.3-l'(Continued);
PART A - PRIMARY CONTAINMENT ISOLATION VALVES i
INB0ARD 00TBOARD ISOL.
PENETRATION FUNCTION ISOLATION ISOLATION MAX.ISOL
' SIGNAL (S),
NOTES PLID-NUMBER PARRIER BARRIER TlME.IF APP.
IF. APP.
AfC)'26)
(20)
D288 DRYWELL H2/02 SAMPLE SV57-233 5
B,H,R,5
,11 57 SV57-243 5
B,H.R,5 11 SV57-295 5
B, f,5 11-
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0308-1 DRYWELL PRESSURE EV42-247A 45 10 42 INSTRUMENTATION 035B TIP PURGE 59-2056(CK)
NA
.59 (DOUBLE "0" RING)
ITV59-231 7
B,11,5 16 035C-G TIP DRIVES XV59-241A-E NA B,H 11,16,21 59 (DOUBLE "0" RING)
XV59-240A-E NA 11,16
-037A-D CRD INSERT LINES BALL CHECK NA 12-47.
(6 ?101 NA 12,22 46
(-
z!6-2102 NA 12,22
['
46-2108 NA 12,22 46-2109 NA 12,22.
038A-D CRD WITHDRAW LINES 46-2115 NA 12,22 46 SDV VENTS & DRAINS 46-2116 NA 22,22 e6-2122 NA 12,22 46-2123 NA 12.22 XV47-2F010 25
'30 47 XV47-2F180 30 30 XV47-2F011 25 30 XV47-2F181 30 30 039A(B)
DRYWELL SPRAY HV51-2F021A(B) 160 4,11 51-I liv 51-2F016A(B) 160 11 040E DRYWELL PRESSURE ilV42-247D 45
.10 :
42 INSTRUMENTATION.
040F-2 CONTAINMENT INSTRUMENT
'HV59-201 45
' H.S 5
59 GAS -' SUCTION HV59-202-7 C H.S Ameixhnent No. 22.
LIMERICK - UNIT 2 3/4 6-23 i
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TABLE 3.6.3-1 (Continued)
C PART A - PRIMARY CONTAINMENT ISOLATION VALVES z
W n
INBOARD OU! BOARD ISOL.
7 PENETRATION FUNCTION ISOLATION ISOLATION MAX.ISOL.
SIGNAL (S),
NOTES PAID NUMBER BARRIER BARRIER TlHE.IF APP.
IF APP.
c5 (SEC)(26)
(20) a to 040G-1 ILRT DATA ACQUISITION 60-2057 NA 11 60 60-2058 NA 11 040G-2 ILRT DATA ACQUISITION 60-2071 NA 11 60
'60-2070 NA 11 040H-1 CONTAINMENT INSTR 8JMENT 59-2005A(CK)
NA 59 GAS SUPPLY - HEADER 'A' HV59-229A 7
C.H.S 042 STANDBY LIQUID CONTROL 48-2F007(CK)
NA 48 (X-116)
HV48-2F006A 60 29 i
0438 MAIN STEAM SAMPLE HV41-2F084 10 B,D 41 HV41-2F085 10 B,0 044 RWCU ALTERNATE 41-2017 NA 5,31 41
. RETURN 41-2016(X-9A, NA X-98)
PSV41-212 NA 045A(8,C,D)
LPCI INJECTION 'A'(B,C,M HV51-2f041A(B,C; NA 9,22 51 D)(CK) liv 51-242A(B,C, 7
9,22 D)
HV51-2F017A 38 (B,C,0) 050A-1 DRYWELL PRESSURE-HV42-2478 45 10 42 INSTRUMENTATION 053 DRYWELL CHILLED WATER HV87-228 60 C.H 11 87 SUPPLY - LOOP 'A' HV87-220A 60 C.H 11 HV87-225A 60 C,H!
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.n-us NOTES 1.
Instrumentation line isolation provisions-consist of an orifice and excess flow-check valve or remote manual isolation valve.
The excess flow-check valve is subjected to operability testing, but no Type C test is performed or required.
The line does not isolate during a d JA and can leak only if the line or instrument should rupture.
Leaktightness of the line is verified during the integrated leak rate test (Type A test).
2.
Penetration is sealed by a blind flange or drar with double 0-ring seals.
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These seals are leakage rate tested by pressurizing between the 0-rings.
3.
Inboard butterfly valve tested in the reverse direction.
4.
Inboard gate valve tested in the reverse direction.
5.
Inboard globe valve tested in the reverse direction.
6.
The MSIVs and this penetration are tested by pressurizing between the valves.
Testing of the inboard valve in the reverse direction tends to unseat the valve and is therefore conservative.
The valves are Type C tested at a test pressure of 22 psig.
3 7.
Gate valve tested in the reverse direction.
8.
Electrical penetrations are tested by pressurizing between the seals.
9.
The isolation provisions for this-penetration consist of two isolation valves and a closed system outside containment.
Because a water seal is maintained in these lines by the safeguard piping fill system, the inboard valve may be tested with water. The outboard valve will be pneumatically tested.
10.
The valve does not receive an isolation signal but remains open to measure containment conditions post-LOCA.
Leaktightness of the penetration is verified during the Type A test.
Type C test is not required.
11.
All isolation barriers are located outside containment.
12.
Leakage monitoring of the control rod drive insert and withdraw line is provided by Type A leakage rate test.
The outboard isolation provisions for the control rod insert and withdraw lines consist of two redundant Type C tested simple check valves located on each main-water header (i.e.
charging, cooling, drive and exhaust).
Type C test is not required for the bal! check valve.
13.
The motor operators on HV-13-209 and HV-13-210 are not connected to any power supply.
14.
Valve is provided with a separate testable seal assembly, with double concentric 0-ring seals installed between the pipe flange and valve flange facing primary containment.
Leakage through these seals is included within the Type C leakage rate for this penetration.
LIMERICK - UNIT 2 3/4 6 al Amendment No. 22
TABLE 3.6.3-1 PRIMARY CONTAINMENT ISOLATION VALVES NOTATION NOTES (Continued) 15.
Check valve used instead of flow orifice.
16.
Penetration is sealed by a flange with double 0-ring seals.
These seals are leakage rate tested by pressurizing between the 0-rings.
Both the TIP Purge Supply (Penetration 358) and the TIP Orive Tubes (Penetrations 35C thru G) are welded to their respective flanges.
Leakage through these seals is included in the Type C leakage rate total for this penetration.
The ball valves (XV-241A thru E) are Type C tested.
It is not practicable to leak test the shear valves (XV-240A thru E) because squib firing is required for closure.
Shear valves (XV-240A thru E) are normally open.
17.
Instrument line isolation provisions consist of an excess flow check valve.
Because the instrument line is connected to a closed cooling water system inside containment, no flow orifice is provided.
The excess flow check valves are subject to operability testing, but no Type C test is performed nor required.
The line does not isolate during a 10CA and can leak only if the line ur instrument should rupture.
Leaktightness of the line is verified uring the integrated leak rate test (Type A test).
18.
In addition to double "0" ring seals, this penetration is tested by pres-surizing volume between doors per Specification 4.6.1.3.
'9.
The RHR system safety pressure relief valves are flanged to facilitate removal and are equipped with double 0-ring seal assen.blies on the flange closest to primary containment.
These seals will be leak rate tested by pressurizing between the 0-rings, and the results added into the Type C total for this penetration.
20.
See Specification 3.3.2, Table 3.3.2-1, for a description of the PCRVICS isolation signal (s) that initiate closure of each automatic isolation valve.
In addition, the following non-PCRVICS isolation signals also initiate closure of selected valves:
EA Main steam line high pressure, high steam line leakage flow, low MSIV-LCS dilution air flow LFHP With dPCI pumps running, opens on low flow in associated pipe, closes when flow is above setpoint LFRC With RCIC pump running, opens on low flow in associated pipe, closes when flow is above setpoint LFCH With CSS pump running, opens on low flow in associated pipe, closes when flow is above setpoint LFCC Steam supply velve fully closed or RCIC turbine stop valve fully closed All power operated isolation valves may be opened o, closed remote manually.
'l LIMERICK - UNIT 2 3/4 6-42
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