ML20215M398
| ML20215M398 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 05/04/1987 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20215M304 | List: |
| References | |
| NUDOCS 8705130218 | |
| Download: ML20215M398 (14) | |
Text
-__ . _ ~_ - -. . _ . . . . . -.-. -- __ _
/ \ UNITED STATES
! NUCLEAR REGULATORY COMMISSION WeASHINGTON, D. C. 30565 LONG ISLAND LIGHTING COMPANY i DOCKt1 MO. 50-322 SH0REHAFlECETAIM W F YTATION >
AMENumtni TO FACILITY UPERATING LICENSE Amendment No. 5 License No. NPF-36
- 1. The Nuclear Regulatory Comission (the Comission) has found thet A. The application for amendment by Long Island Lighting Company ,
(thelicensee),datedJanuary 21, 1987, 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 I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C. Thereisreasonableassurance(i)thattheactivitiesauthorizedby this amendment can be conducted without endangering the health and safety of the public, and (ii) that suck activitiu will be conducted in compliance with the Comission's regulations; D. The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied, j
j 2. Accordingly, the license is amended by changes to the Technical Specifications
- as indicated in the attachment to this license amendment, and paragraph P.C.(2) i of Facility Operating License No. NPF-36 is hereby amended tn read as follows
Technical Specifications i
The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 5 are hereby incorporated into this ifcense.
Long Island lighting Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
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L2 - t 3 .' This license amendment is effective as of its date of issuance. FOR THE NUCLEAR REGULATORY COMMISSION
/s/
Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance: May 4, 1987
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- 3. This license amendment is effective as of its dete of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications - Date of Issuance: May 4, 1987 r
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[' l l ATTACM ENT TO LICENSE AMENDMENT NO. 5 j FACILITY OPERATING LICENSE NO. NPF-36 DOCKET NO. 50-322 Replace the following pages of the Appendix "A" Technical Specifications with 1 the attached pages. The revised pages are identified by Amendment number and ; contain vertical lines indicating the area of change. Overleaf pages provided to maintain document completeness.* Remove Insert 3/4 3-11 3/4 3-11 3/4 3-12 3/4 3-12* - 3/4 3-15 3/4 3-15* 3/4 3-16 3/4 3-16 3/4 3-19 3/4 3-19* 3/4 3-20 3/4 3-20 3/4 3-23 3/4 3-23 3/4 3-24 3/4 3-24* B 3/4 3-7 B 3/4 3-7* B 3/4 3-8 B 3,4 3-8
TABLE 3.3.2-1 !! ISOLATION ACTU_4 TION INSTRUMENTATION
- VALVE GROUPS MINIMUM APPLICABLE 3E OPERATED BY OPERABLE CHANNELS OPERATIONAL TRIP FUNCTION - SIGNAL PER TRIP SYSTEM (a) CONDITION ACTION
- 1. PRIMARY CONTAINMENT ISOLATION
{} sa a. Reactor Vessel Water Level I
- 1) Low Low, Low Level 1 1, 14 2 1,2,3 20
- 2) Low Low Level 2 10, 11 (b)(c) ? 1, 2, 3 22
- b. Drywell Pressure - High 10, 11 (b)(c)(d) e 1, 2, 3 22
- c. Main Steam Line
- 1) Radiation - High 1, 10, 14 2 1,2,3 21
- 2) Pressure - Low 1, 14 2 1 23
- 3) Flow - High 1, 14 2/line 1,2,3 21
- d. Main Steam Line Tunnel Temperature - High 1, 14 2 1,2,3 21 R' e. Main Steam Line Tunnel A Temperature - High 1, 14 2 1,2,3 21 4' f. Main Steam Line
[d Area Turbine Bldg. I Temperature - High 1, 14 2 1,2,3 21 ;
- g. Main Steam Tunnel Penetration Area Temperature - High 14 1(h)(i) 1, 2, 3 22
- h. Condenser Vacuum - Low 1, 14 2 1, 2*, 3* 21
- i. Manual Initiation 1 2/ group 1, 2, 3 24 10, 11 1/ group 1,2,3 25 14 ; 1/ group 1, 2, 3 26 j[ 2. SECONDARY CONTAINMENT ISOLATION .
E a. Drywell Pressure - High 9(b)(c)(d) 2 1,2,3 27 8 b. Reactor Vessel Water A Level - Low Low, Level 2 9(b)(c)(d) 2 1, 2, 3, and # 27 z c. Refueling Floor Exhaust P Radiation - High 9(b)(c)(d) 1(i) 1, 2, 3, and ** 27 ui d. Reactor Building Differ-ential Pressure - Low 9(b)(c)(d) 1(1) 1, 2, 3, and ** 27
- e. Manual Initiation 9 1/ group 1 2, 3, and ** 27
TABLE 3.3.2-1 (Centinued)
!! ISOLATION ACTUATION INSTRUMENTATION
!! VALVE GROUPS MINIMUM APPLICABLE R OPERATED BY OPERABLE CHANNELS OPERATIONAL 7 TRIP FUNCTION SIGNAL PER TRIP SYSTEM (a) CONDITION ACTION
@ 3. REACTOR WATER CLEANUP SYSTEM ISOLATION q
- s. a. A Flow - High 3, 4 1(i) 1, 2, 3 22
- b. Heat Exchanger / Pump Area Temperature - High 3, 4 3 1,2,3 22
- c. SLCS Initiation 4 N.A. 1, 2, 3 22
- d. Reactor Vessel Water .
Level - Low Low, level 2 3, 4 2 1, 24 3 22
- e. Main Steam Tunnel Penetration Area gj Temperature - High 3, 4 1/ group 1,2,3 22 u, f. Manual Initiation 3, 4 / group 1,2,3 26 b
- 4. REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION
- a. RCIC Steam Line Flow - High 6, 15 1(1) 1, 2, 3 22
- b. RCIC St'eam Supply Pressure - Low 6, 12(e),15 2 1,2,3 22
- c. RCIC Turbine Exhaust Diaphragm Pressure - High 6 ,15 2 1,2,3 22
- d. RCIC Equipment Area ,
Temperature - High 6, 15 1(1) 1, 2, 3 22
- e. RCIC Elevation 63' Area Temperature - High 6, 15 1(1) 1, 2, 3 22
- f. Drywell Pressure - High 12(e) 2 1,2,3 22
- g. Manual Initiation 15(f) 1/ group 1,2,3 26 e e
TABLE 3.3.2-1 (Continued) ISOLATION ACTUATION INSTRUMENTATION ACTION STATEMENTS ACTION 20 - Be.in at within theleast nextHOT SHUTOOWN within 12 hours'and in COLD SHUTDO 24 hours. ACTION 21 - Be in at least STARTUP with the associated isolation valves closed within 6 hours or be in at least HOT SHUT 00WN within 12 ACTION 22 - hours and-in COLD SHUTOOWN within the next 24 hours. Close the affected system isolation valves within I hour ACTION 23 - and declare the affected system inoperable. ACTION 24 - Be in at least STARTUP within 6 hours. Restore the manual initiation function to OPERABLE status within 48 hours or be in at least HOT SHUTOOWN within the next ACTION 25 - 12 hours and in COLD SHUTDOWN within the following 24 hours. Restore the manual initiation function to OPERABLE status within 1 8 hours or be in at least HOT SHUT 00WN within the next 12 hours and in COLD SHUTDOWN within the following 24 hours. ACTION 26 - Restore the manual initiation function to OPERABLE status within 8 hours or close the affected system isolation valves within ACTION 27 - the next hour and declare the affected system inoperable. operatir,g SECONDARY Establish within I hour. CONTAINMENT INTEGRITY with the R65VS ACTION 28 - Lock the affected system isolation .lves closed within 1 hour and declare the affected system inoperable. TABLE NOTATIONS May valves
'stop be bypassed closed.with reactor steam pressure s 1043 psig and all turbine When handling irradiated fuel in the secondary containment and during CORE
# ALTERATIONS and openstions with a potential for draining the reactor vessel.
During reactor CORE vessel.ALTERATIONS and operations with a potential for draining the (a) A channel may be placed in an inoperable status for up to 2 hours for L
. required surveillance without placing the trip system in the tripped con- ,
dition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter. - (b) Also actuates the RBSYS. (Not applicable to one channel systems.) (c) Also actuates the control room emergency filtration system in the pressurization mode of operation. (d) Also actuates reactor butiding normal ventilation system isolation valves per Table 3.6.5.2-1. (e) Requir'es RCIC/HPCI systes steam supply pressure-low coincident with drywell pressure-high. (f) Manual initiation isolates outboard steam supply valve and bypass valve (g) . Individual only and-only with a coincident reactor vessel water level-low low, level 2. valve controls. (h) One sensor and one trip channel. { (i) A channel may be placed 4n an inoperable status for up to 2 hours for required surveillance without placing the trip system in the tripped condition. SHOREHAM - UNIT 1 3/4 3-15
TABLE 3.3.2-2
$ ISOLATION ACTUATION INSTRUMENTATION SETPOINTS M
j ALLOWABLE TRIP FUNCTION TRIP SETPOINT i VALUE E 1. PRIMARY CONTAINMENT ISOLATION
- a. Reactor Vessel Water Level
- 1) Low Low Low, Level 1 > -132.5, inches * > -139.5 inches
- 2) Low Low, Level 2 5 -38 inches
- i -45 inches
- b. Drywell Pressure - High 31.69psig 51.89psig
- c. Main Steam Line i
- 1) Radiation - High < 3.0 x full power background < 3.6 x full power background
- 2) Pressure - Low > 825 psig -
> 805 psig
- 3) Flow - High -7 106.0 psid 7 109.0 psid
- d. Main Steam Line Tunnel -
Temperature - High -< 155*F** < 161*F** t*
- e. Main Steam Line Tunnel -
A Temperature - High -< 50*F < 56*F T f. Main Steam Line - M Area Turbine B1dg. Temperature - High -< 155*F** < 161*F**
- g. Main Steam Tunnel -
Penetration Area y Temperature - High < 175*F** < 181*F**
- h. Condenser Vnctum - Low I 8.5 inches Hg vacuum i 7.6 inches Hg vacuum
- 1. Manual Initu t. ion H.A. R.A.
> 2. SECONDARY CONTAINMENT ISOLATION ,
12 E a. Drywell Pressure - High
< 1.69 psig 2 ' ~< 1.89 psig
- b. Reactor Vessel Water S Level - Low low, level 2 -> -38 inches * > -45 inches
- - c. Refueling Floor Exhaust -
P Radiation - High < 35 mR/hr** < 45.5 mR/hr** tr. d. Reactor Building Differ- -F 0.30 inch H 2O I 0.25 inch H 2O
- ential Pressure - Low below ATM - below ATM
- e. Manual Initiation N.A. ,
N.A. e
- t
TABLE 3.3.2-2 (Continued) E gg ISOLATION ACTUATION INSTRUMENTATION SETPOINTS 9 3; TRIP FUNCTION ALLOWABLE-TRIP SETPOINT VALUE
-4
- 7. REACTOR BUILDING CLOSED LOOP COOLING WATER SYSTEM /RHR CONTAINMENT SPRAY ISOLAll0N
- a. Drywell Pressure - High 1 1.69 psig i 1.89 psig
- b. Reactor Vessel Water Level-Low Low Low Level 1 +
1 - 132.5 inches
- 1 - 139.5 inches
- c. RBCLCW Head Tank Level - Low Low 15 feet-9 inches 1 5 feet-3 inches
- d. Manual Initiation NA NA
- 8. POST ACCIDENT SAMPLING SYSTEM ISOLATION
- a. Reactor Vessel Water Level -
Low Level 3 2 12.5 inches
- 1 11 inches
- b. Drywell Pressure - High 5 1.69 psig w i 1.89 psig j; c. Manual Initiation NA NA "See Bases Figure B 3/4 3-1.
** Initial setpoint. Final setpoint to be' determined during startup test program. Any required change to this setpoint shall be submitted to the Gommission within 90 days of test completion.
*** Corrected for cold water head with reactor vessel flooded.
TABLE 3.3.2-3 ISOLAT?ON SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION RESPONSE TIME (Seconds)#
- 1. PRIMARY CONTAINMENT ISOLATION
- a. Reactor Vessel Water Level Low Low Low, Level 1 < 1.0*/< 13(,).,
Low Low, Level 2 < 13(a)"
- b. Drywell Pressure - High 13(a)
- c. Main Steam Line
- 1) Radiation - High(b) < 1.0*/< 13(a)**
- 2) Pressure - Low 7 1.0*/7 13(a),, ,
- 3) Flow - High 30.5*/513(*),,
- d. Main Steam Line Tunnel Temperature - High N.A.
- e. Main Steam Line Tunnel A Temperature - High N.A.
- f. Main Steam Line Area Turbine Bldg.
Temperature - High N.A.
- g. Main Steam Tunnel Penetration Area Temperature - High N.A.
- h. Condenser Vacuum - Low N.A.
- i. Manual Initiation N.A.
- 2. SECONDARY CONTAINMENT ISOLATION
- a. Drywell Pressure - Hiti < 13I ') ;.
- b. Reactor Vessel Water Level - Low Low, Level 2 7 13(a)
- c. Refueling Floor Exhaust Radiation - High(b) 7 13(a)
- d. Reactor Building Differential Pressure - Low R.A.
- e. Manual Initiation N.A.
- 3. REACTOR WATER CLEANUP SYSTEM ISOLATION <
- a. A Flow - High N.A.
- b. Heat Exchanger / Pump Area Temperature - High H.A. -
- c. SLCS Initiation
- d. Reactor Vessel Water Level - Low Low, Level 2 N.A.(a)
< 13
- e. Main Steam Tunnel Penetration Area Temperature - High N.A.
- f. Manual Initiation N.A.
- 4. REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION
- a. RCIC Steam Line Flow - High < 13(a)#
- b. RCIC Steam Supply Pressure - Low I 13(a)
- c. RCIC Turbine Exhaust Diaphragm Pressure - High R.A.
- d. RCIC Equipment Area Temperature - High N.A.
- e. RCIC Elevation 63' Area Temperature - High N.A.
- f. Drywell Pressure - High N.A.
- g. Manual Initiation N.A.
SHOREHAM - UNIT 1 3/4 3-20 Amendment No. 5
}
l TABLE 4.1.2.1-1
$ ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS A
I CHANNEL OPERATIONAL N CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH TRIP FUNCTION - CHECK TEST CALIBRATION SURVEILLANCE REQUIRED 2 ! 1. PRIMARY CONTAINMENT ISOLATION g a. Reactor Vessel Water level-i 1) Low Low Low Level 1 S M R 1,2,3 Low Low, Level 2
- 2) S M R 1,2,3
- b. Drywell Pressure - High 5 M R 1,2,3
- c. Main Steam Line
- 1) Radiation - High S M R 1,2,3
- 2) Pressure - Low N.A. M Q 1
- 3) Flow - High S M R 1,2,3
- d. Main Steam Line Tunnel Temperature - High 5 M R 1,2,3 t' e. Main Steam Line Tunnel
- 6 Temperature - High 5 H R 1,2,3 Y f. Main Steam Line O Area Turbine Bldg.
Temperature - High S M R 1, 2*, 3*
- g. Main Steam Tunnel Penetration Area Temperature - High S M R 1, 2 3
- h. Condenser Vacuum - Low N.A. M Q .1, 2 4 , 3*
- i. Manual Initiation N.A. R N.A. 1,2,3 g 2. SECONDARY CONTAINMENT ISOLATION
& a. Drywell Pressure - High 5 M R 1,2,3 2 b. Reactor Vessel Water A Level - Low Low, Level 2 S' M R 1, 2, 3, ano #
2 c. Refueling Floor Exhaust
. Radiation - High S M R 1, 2, 3, and **
- d. Reactor Building Differ-ential Pressure - Low S M R 1, 2, 3, and **
- e. Manual Initiation N.A. R N.A. 1, 2, 3, and **
O
' TABLE 4.3.2.1-1 (Continued) ISOLATION ACTUATION INSTRUMENTATION-SURVEILLANCE REQUIREMENTS h CHANNEL
$ CHANNEL FUNCTIONAL CHANNEL
. OPERATIONAL CONDITIONS FOR WHICH
, TRIP FUNCTIOh CHECK TEST CALIBRATION SURVEILLANCE REQUIRED E 3. REACTOR WATER CLEANUP SYSTEM ISOLATION
] a. A Flow - High N. A. M Q 1,2,3
- b. Heat Exchanger / Pump Area Temperature - High N.A. M Q 1,2,3
- c. SLCS Initiatior. N.A. R N.A. 1,2,3
- d. Reactor Vessel Water .
Level - Low Low, level 2 5 M R 1, 2, 3
- e. Main Steam Tunnel Penetration Area g Temperature - High 5 M R 1,2,3 w f. Manual Initiation N.A. R N.A. 1, 2, 3
) h 4. REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION
- a. RCIC Steam Line Flow - High N.A. M '1, 2, 3 Q
- b. RCIC Steam Supply Pressure -
4 Low . N.A. M Q 1, 2, 3
- c. RCIC Turbine Exhaust Diaphragm Pressure - High N.A. M Q 1,2,3
- d. RCIC Equipment Area Temperature - High ;, 5 M R 1,2,3
- e. RCIC Elevation 63' Area -
Temperature - High 5 M R. 1, 2, 3
- f. Drywell Pressure - High N.A.
M Q 1, 2, 3
, g. Manual Initiation N.A. R N.A. 1, 2, 3
jic
- k.
t r INSTRUMENTATION BASES MONITORING INSTRUMENTATION (Continued) 3/4.3.7.13 SAFETY PARAMETER DISPLAY SYSTEM This system is provided as an aid to the operating personnel in evaluating the plant status by display of computer generated graphics based on safety-related data available to the plant process computer. 3/4.3.8 TURBINE OVERSPEED PROTECTION SYSTEM This specification is provided to ensure that the turbine overspeed protection system instrumentation and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed. Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety related components, equipment, or structures. 3/4.3 9 FEEDWATER SYSTEM / MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION The feedwater system / main *,urbine trip system actuation instrumentation is provided to initiate action of the feedwater system / main turbine trip system in the event of reactor vessel water level high - level 8. 4. e 4 SHOREHAM - UNIT 1 B 3/4 3-7 -
- e e.CTt Y
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