ML20056B369
| ML20056B369 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 08/16/1990 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20056B370 | List: |
| References | |
| NUDOCS 9008280191 | |
| Download: ML20056B369 (8) | |
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k UNITED STATES I
f ') > r, / y g NUCLEAR REGULATORY COMMISSION n
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PHILADELPHIA ELECTRIC COMPANY l
DOCKET NO. 50-352 LIMERICK GENERATIllG STATION, UNIT 1 APEtJDMENT TO FACILITY OPERATING LICENSE
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Amendment No. 42 License No. NPF-39 1.
The Nuclear Regulatory Comission (the Comission) has found that A.
The application for amendment by Philadelphia Electric Company (the licensee) dated June 14, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter it B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 (ii) 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 istuance of.this amendment is in accordance with 10 CFR Part 51 of the Comise. ton's regulations and all applicable requirements have been satisfied.
2.
Accordingly. the license is amended by changes to the Technical Specifications asindicatedintheattachmenttothislicenseamendment,andparagraph2.C.(2) of Faciitty Operating License No. NPF-39 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 42
, are hereby incorporated into this license. Philadelphia Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
900B280191 900016 PDR ADOCK 05000352 l
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. 3.
This license amendrent is effective Septerber 30, 1990.
FOR THE NUCLEAR REGULATORY COMMISSION 3
Original signed by Walter R. Butler, Director Project Directorate 1-2 Division of Reactor Projects - I/II
Attachment:
Charges to the Technical Specificatiens Date of Issuance:
August 16, 1990 1
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. 3.
This license amendment is effective September 30, 1990.
FOR THE NUCLEAR REGULATORY COMMISSION
&d Walter R. Butler, Director Project Directorate I-?
Division of Reactor Projects - 1/11
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Attachment:
Changes to the Technical Specifications Date of Issuance:
August 16, 1990 1
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ATTACHMENT TO LICENSE AMENDMENT NO. 42 FACILITY OPERATING LICENSE'NO. NPF-39 DOCKET NO. 50-352 Replace the following pages of the Appendix A Technical Specifications with the attached pages. -lhe revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Overleaf pages are provided to maintain document completeness.*
Pemove Insert 3/4 6-23 3/4 6-23 3/4 6-24 3/4 6-24*
l 3/4 6-41 3/4 6-41 3/4 6-42 3/4 6-42*
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TABLE 3.6.3-1 (Continued) y E
g PART A - PRIMARY CONTAIPMENT ISOLATION VALVES M
x INBOARD OUTBOARD ISOL.
PENETRATION FUNC1 ION ISOLATION ISOLATION MAX.ISOL.
SIGNAL (S),
NOTES P&IO g
NUPEER.
BARRIER BARRIER-TINE.IF APP.
IF APP.
.g (SEC)(26)
(20) 0288 DRYWELL H2/02 SAMPLE SV57-133 5
B,H,R,5 11 57 SV57-143 5.
8,H,R,5 11 SV57-195 5
B,H,R,5 11 0308-1 DRYWELu PRESSURE HV42-147A 45 10 42 INSTRUMENTtTION 035B TIP PURGE 59-1056(CK)
NA 59 (DOUBLE "0" RING)
HV59-131 7
B,H,5 16 1 035C-G TIP DRIVES XV59-141A-E NA B,H 11,16,21 59
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(DOUBLE "0" RING) y XV59-140A-E NA 11,16 i
037A-D CRD INSERT LINES BALL CHECK NA 12 47 46-1101 NA 12,22 46-1102 NA 12,22 46-1108 NA 12,22 46-1109 NA 12,22 038A-D CRD WITHORAW LINES 46-1115 NA 12,22 47 SDV VENTS & DRAINS 46-1116 NA 12,22 i
46-1122 NA 12,22 46-1123 NA 12,22 XV47-IF010 25 30 s
XV47-1F180 30 30 XV47-IF011 25 30 i
(
XV47-1F181 30 30 Y
039A(B)
DRYWELL SPRAY HV51-1F021A(B) 160 4,11 51 HV51-1F016A(B) 160 11 i
040E DRYWELL PRESSURE-HV42-147D 45 10 42
,U INSTRUMENTATION g 040F-2 CONTAllMENT INSTRUMENT HV59-101 45 C,H,5 5
59 GAS -SUCTION HV59-102 7
C.H,5
TABLE 3.6.3-1 (Continued) c; 3;
PART A - PRINARY CONTAINMENT ISOLATION VALVES iS, INBOARD DUTBOARD ISOL.
r
PENETRATION FUNCTION ISOLATION ISOLATION MAX.ISOL.
SIGNAL (S),
NOTES P&l0
' NUMBER BARRIER BARRIER TIME.IF APP.
IF APP.
Ej (SEC)(26)
(20) e
-.040G-1 ILRT DATA ACQUISITION 60-1057 11 60 60-1058 h4 11 I-1040G-2 ILRT DATA ACQUISITION 60-1071 NA 11 60 60-1070 NA 11 040H-1 CONTAINMENT INSTRUMENT 59-1005A(CK)
NA 59 GAS SUPPLY - HEADER 'A' HV59-129A 7
C,H,5 u,042 STAN0BY LIQUID CONTROL 48-1F007(CK)
NA 48
)
3:
(X-116)
HV48-1F006A 60 29 0438 MAIN STEAM SAMPLE HV41-1F084 10 8,D 41 HV41-1F085 10 8,0 044 RWCU ALTERNATE 1017 NA 5,31 41 RETURN 41-1016(X-9A, NA X-98)
PSV41-112 NA 045A(8,C,D)
LPCI INJECTION 'A'(8,C,D) tiV51-1F041A(B,C, MA 9,22 51
$I D)(CK)
HV51-142A(B,C, 7
9,22
.NI D) m H'/51-1F017A 38
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(B,C,0)
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, ca~ 050A-1 DRYWELL PRESSURE HV42-1478 45 10 42 S."
INSTRUMENTATION ca E 053 DRYWELL CHILLED WATER HV87-128 60 C,H I?
87 E,',
SUPPLY - LOOP 'A' HV87-120A 60 CH 11 te "V87-125A 60 CH 11 8
_ _. _. - - _ _ _ _ _ -. _ - _ _ _ _ _ _ _. - - _.. _ _. _. _ _ _ - - _ - - _ _ _ _ - -. - _ _ -. - - _ - _ _. - - _ _ - - - _ - _ _ _ _ _ _ _ _ - _ _ _ _ _ - - -. - _ _ _ _ + _, --
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TABLE 3.6.3-1 PRIMARY LONTATRRD F T5UEXTION VALVES NOTATION l
NOTES 1.
Instrumentation line isolation provisions consist of an orifice and i
excess flow-check valve or remote manual isolation valve.
The excess flow-check valve is subjected to operability testing, but no Type C test l
j is performed or required.
The line does not isolate during a LOCA 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 door with double 0-ring seals.
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 tne reverse direction tends to unseat the valve and is therefore conservative.
The valves are Type C tested at a test pressure of 22 psig.
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 penetra-tion 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 consists 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 ball check valve.
13.
The motor operators on HV-13-109 and HV-13-110 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.
LIHERICK - UNIT 1 3/4 G 4 Amendment No. 42
TAELE 3..3-1 6
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 Drive Tubes (Penetrations 35 C i
i thru G)are welded to their respective flanges.
5 is included in the Type C leakage rate total for this penetration. Leakage through, The ball valves (XV-141A thru E) are Type C tested.
It is not practicable to leak test the shear valves (XV-140A thru E) because squib firing is required for closure.
Shear valves (XV-140A thru E) are normally open.
17.
Iastrument line isolation provisions consist of an excess flow check valve.
Because the instrument line is connected to a closed cooling water system i
Inside containment, no flow orifice is provided.
The excess flow chcck valves are subject to operability testing, but no Type C test is performed nor required.
if the-line or instrument should rupture.The line does not isolate during a L Leaktightness of the line is verified during the integrated leak rate test (Type A test),
i 18.
In addition to double "0" ring seals, this penetration is tested by pres-surizing volume between doors per Specification 4.6.1.3.
19.
The RHR system safety pressure relief valves which are flanged to facilit3te removal will be equipped with double 0-ring seal assemblies on the flange
'i 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 l
total for this penetration.
i 20.
See Specification 3.3.2. Table 3.3.2-1, for a description of the PCRVICS
[
isolation si In addition,gnal(s) that initiate closure of each automatic isolation valve.
l 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 l
LFHP With HPCI 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 valve fully closed or RCIC turbine stop valve fully closed All power operated isolation valves may be opened or closed remote manually.
LIMERICK - UNIT 1 3/4 6-42 Amendment No. 29, 33 OCT 3 01989