ML19347F233
| ML19347F233 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 05/08/1981 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19347F234 | List: |
| References | |
| NUDOCS 8105180012 | |
| Download: ML19347F233 (15) | |
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V BALTIM0RE GAS AND ELECTRIC COMPANY DOCKET N0. 50-317 CALVERT C;f PS NUCLEAR POWER STATION, UNIT NO.1 t
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 54 License Nos. DPR-53 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applications for amendment by Baltimore Gas and Electric Company (the licensee) dated January 22 and November 10 and 25, 1980, as supplemented by numerous other letters, comply 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 (1) 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; ared 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.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the. attachment to this license amendment, and paragraph,2.C.(2) of Facility Operating License No. DPR-53 is hereby amended to read as follows:
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. i (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 54, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendmer,t is effective on June 1,1981.
FOR THE NUCLEAR REGULATORY COMMISSION 7
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- x Robert A. Clark, Chief Operating heactor Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: May 8, 1981 t
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BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-318 CALVERT CLIFFS NUCLEAR POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE t
Amendment No.37 License Nos. DPR-69 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applications for amendment by Baltimore Gas and Electric Company (the licensee) dated January 22 and November 10 and 25, 1980, as supplemented by numerous other letters, comply 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 thd 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 i
and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; l
D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safetiy 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.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.2 of F.acility Operating License No. OPR-69 is hereby amended to read as follows:
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Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 37, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective on June 1,1981.
FOR THE NUCLEAR REGULATORY COMMISSION t
w Robert A. Clark, Chief Operating Reactor Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: May 8, 1981 i
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ATTACHMENT TO LICENSE AMENDMENTS NO. 54 AND 37 NO.
FACILITYOPERAtINGLICENSESNO.DPR-53ANDDPR-69 DOCKETS NO. 50-317 AND NO. 50-318 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document ccmpleteness.
Pages 3/4 3-14 3/4 3-19 3/4 3-20 3/4 3-21 3/4 3-23 3/4 7-5 d
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5 TABLE 3.3-3 (Continued) hh ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTUMENTATION mm EE MINIMUM nn CC TOTAL NO.
CHAk1ELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 6. CONTAIN!1ENT PURGE N EE VALVES ISOLATION na ra - a. Manual (Purge Valve Control Switches) 2/ Penetration 1/ Penetration 2/ Penetration 1, 2, 3, 4 6 b'. Containment Radiation - High Area Monitor 4 2 3 6 8 7. LOSS OF POWER wS a. 4.16 kv Emergency Bus Undervoltage (Loss of w g Voltage) 4/ Bus .2/ Bus 3/ Bus 1, 2, 3 7* b. 4.16 kv Emergency Bus Undervoltage (Degraded Voltage) 4/ Bus 2/ Bus 3/ Bus 1, 2, 3 7* EE e my
- Containment purge valve isolation is also initiated by SIAS (functional units 1.a.1.b, and 1.c).
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m w y i nn [](( TABLE 3.3-3 (Continued) ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION PP MM MINIMUM gy TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION c: c: 25 25 -i -d 8. CVCS ISOLATION ro -. ~ a. Manual (CVCS 1/ Valve 1/ Valve 1/ Valve 1, 2, 3, 4 6 Isolation Valve Control Switches) b. West Penetration 4 2 3 1,2,3,4 7 Room / Letdown Heat ]; Exchanger Room Pressure - High I 9. AUXILIARY FEEDWATER pp a. Manual 2 1 2 1,2,3 6 m o E $. b. Steam Generator j y Level - Low 4 2 3 1, 2, 3 7 r o O 2 .,,,. ~.. -.. -..
.i g ~ Qg TABLE 3.3-4 (Continued) GG Og ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES Hw nn CC ALLOWABLE h3 FUNCTIONAL UNIT TRIP VALUE VALUES i, 8. CVCS ISOLATION ec il 5 West Penetration Room / '-< 0.5 psig < 0.5 psig Letdown Heat Exchanger Room Pressure - High 9. AUXILIARY FEEDWATER a. Manual Not Applicable Not Applicable 'b. Steam Generator Level - Low -39.6 to -49.5 in -39.6 to -49.5 in g b 8a RE D8 r > r+ P Y: i
TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 1. Manual a. SIAS Safety Injection (ECCS) Not Applicable i b. CSAS Containment Spray Not Applicable c. CIS Containment Isolation Not Applicable d. RA$ Containment Sump Recirculation Not Applicable 3 e. Auxiliary Feedwater Initiation Not Applicable l 2. Pressurizer Pressure-Low a. Safety Injection (ECCS) < 30*/30** 3. Containment Pressure-High a. Safety Injection (ECCS) 1 30*/30** b. Containment Isolation 1 30 c. Containment Fan Coolers 1 35*/10** 4. Containment Pressure--High a. Containment Spray 1 60*/60** (1) 5. Containment Radiation-High r i a. Containment Purge Valves Isolation 15 i ~. l CALVERT CLIFFS - UNIT 1 3/4 3-20 Amendment No. Ah, 54 CitLVEKT C'.:FFS - ll;!IT 2 Amendment I:o. /J,37
TABLE 3.3-5 (Continued) ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 6. Steem Generator Pressure-Low a. Main Steam Isolation 5, 6. 9 b. Feedwater Isolation 5, 80 7. Refueling Water Tank-Low a. Containment Sump Recirculation 5, 80 8. Reactor Trip a. Feedwater Flow Reduction to 5% f, 20 9. Loss of Power a. 4.16 kv Emergency Bus < 2.2 ~- Undervoltage (Loss of Voltage) b. 4.16 kv Emergency Bus --< 8.4 Undervoltage (Degraded Voltage) 10. Steam Generator Level - Low a. Auxiliary Feedwater System 5,360*/360**(2) TABLE NOTATION
- Diesel generator starting and sequence loading delays included.
- Diesel generator starting and sequence loading delays not included.
Offsite power available.
- Response time measured frgm the incidence of the undervoltage condition to the diesel generator start signal.
(1 ) Header fill time not included. (2) Includes time delay of 3 to 5 minutes. CALVERT CLIFFS - UNIT 1 Amendment No. 48 54 CALVERT CLIFFS - UNIT 2 3/4 3-21 Amendment No.de. 37
i TABLE 4.3-2 hh ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTAION SURVEILLANCE REQUIREMENTS MM CHANNEL MODES IN WHICH Qg CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE n n CHECK CALIBRATION TEST REQUIRED Cc FUNCTIONAL UNIT AM m m 1. SAFETY INJECTION (SIAS) ' i a. Manual (Trip Buttons) N.A. N.A. R N.A. Eg b. Containment Pressure - High S R M 1,2,3 c. Pressurizer Pressure - Low S R M 1, 2, 3 p ]- d. Automatic Actuation Logic N.A. N.A. M(1)(3) 1, 2, 3 m 2. CONTAINMENT SPRAY (CSAS) a. Manual (Trip Buttons) N.A. N.A. R N.A. b. Containment Pressure -- High S R M 1,2,3 c. Automatic Actuation Logic N.A. N.A. M(1) 1, 2, 3 l 3. C0tiTAINMENT ISOLATION (CIS) # %d a. Manual CIS (Trip Buttons) N.A. N.A. R N.A. N b. Containment Pressure - High S R M 1,2,3 c. Automatic Actuation Logic N.A. N.A. M(1)(4) 1, 2, 3 ~ 4. MAIN STEAM LINE ISOLATION (SGIS) a. Manual SGIS (MSIV Hand FF Switches and Feed Head 32 Isolation Hand Switches) N.A. N.A. R N.A. l 2i b. Steam Generator Pressure - Low S R M 1, 2, 3 l 22 c. Automatic Actuation Logic N.A. N.A. M(1)(5) 1, 2, 3 r r O O f Containment isolation of non-essential penetrations is also ini,tiated by SIAS (functional units wm ( 1.a and 1.c). j + - - - - - - -,. -.. - .v.
99 TABLE 4.3-2 (Continued) rj- - gg ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS-PP CHANNEL MODES IN WHICH ~ ~, CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE m?G FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED C C 55 5. CONTAINMENT SUMP
- j RECIRCULATION (RAS) a.
Manual RAS (Trip Buttons) N.A. N.A. R N.A. b. Refueling Water Tank - Low N.A. R M i, 2, 3 c. Automatic Actuation Logic N.A. N.A. M(1) 1, 2, 3 6. CONTAINMENT PURGE VALVES ISOLATION w a. Manual (Purge Valve Control 2 Switches) N.A. N.A. R N.A. b. Containment Radiation - High w A> Area Monitor S R M 6 w 7. LOSS OF POWER a. 4.16 kv Emergency Bus Undervoltage (Loss of Voltage) N.A. R M 1,2,3 b. 4.16 kv Emergency Bus Undervoltage (Degraded Voltage) N.A. R M 1, 2, 3 8. CVCS ISOLATION N.A. R M 1,2,3,4 West Penetration Room / Letdown Heat Exchanger (( Room Pressure - High E$ $j 9. AUXILIARY FEEDWATER a. Manual N.A. N.A. R N.A. g= b. Steam Generator Level - Low S R M 1,2,3 %p 50 di e nt a m. ment purge valve isolation is also initiated by SIAS (functional units 1.a,1.b and 1.c).
e TABLE 4.3-2 (Continued) TABLE NOTATION (1) The logic circuits shall be tested manually at least once per 31 days. (3) SIAS logic circuits A-5, B-5, A-10 and B-10 may be exempted from testing during operation; however, these logic circuits shall be tested at least once per 18 months during shutdown. (4) CIS logic circuits A-5 and B-5 may be exempted from testing during operation; however, these logic circuits shall be tested at least once per 18 months during shutdown. (5) SGIS logic circuits A-1 and B-1 may be exempted from testing during operation; however, these logic circuits shall be tested at least once per 18 months during shutdown. CALVERT CLIFFS - UNIT 1 CALVERT CLIFFS - UNIT 2 ' 3/4 3-24 Amendment No. 3
-PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2 At least two steam turbine driven steam generator auxiliary feed-water pumps and associated flow paths shall be OPERABLE. APPLICABILITY: MODES 1, 2 and 3. ACTION: With one auxiliary feedwater pump inoperable, restore at least two a. auxiliary feedwater pumps to OPERABLE status within 72 hours or be in HOT SHUTDOWN within the next 12 hours. b. Whenever a subsystem is inoperable for the performance of periodic testing (i.e. manual discharge valve closed for pump discharge head test) a dedicated operator will be stationed at the local station (i.e. closed valve), with direct communication to the Control Room, to return the subsystem to normal upon instruction from the Control Room. Upon completion of any testing, the subsystem (valve) will be returned to its proper position and verified in its proper position by an independent operator check. SURVEILLANCE REQUIREMENTS 4.7.1.2 Each auxiliary feedwater pump shall be demonstrated OPERABLE: a. At 'least once per 31 days by: l'. Verifying that each steam turbine driven pump develops a Total Dynamic Head of > 2800 ft. on recirculation flow when the. secondary steam suliply pressure is greater than 800 psig. 2. Cycling each testable, remote operated valve that is not in its operating' position through at least one complete cycle.
- 3. ~ Verifying that each valve (manual, power operated or automatic) in the direct. flow path is in its correct position.
b. Before entering MODE 3 after a COLD SHUTDOWN of at least 14 days by completing a flow test that verifies the flow path from the condensate storage tank to the steam generators. c. At least once per 18 months by: ~ 1. Verifying that each automatic. valve in the flow puh actuates to its correct position upon receipt of each audl <ry feed-water actuation ~ test signal. 2. Verifying that each auxiliary feedwater pump starts as designed automatically upon receipt of each auxiliary feedwater actua-l tion test signal. h/BIElm-Mll1 3/4 7-s 2:RaentHo.5; 3 l
8 0 ~ PLANT SYSTEMS CONDENSATE STORAGE TANK LIMITING CONDITION FOR OPFRATION 3.7.1.3 The No. 12 condensate storage tank (CST) shall be OPERABLE with a' minimum contained water volume of 150,000 gallons per unit. l APPLICABILI'TY: MODES 1, 2 and 3. i ACTION: With the No. 12 condensate storage tank inoperable, within 4 hours 1 either: a. Re' store the CST to OPERABLE status or be-in HOT SHUTDOWN { within the next 12 hours, or b. Demonstrate the OPERABILITY of the No. 11 condensate storage tank as a backup supply to the auxiliary feedwater pumps and restore the No. 12 condensate storage tank to OPERABLE status within 7 days or be in HOT SHUTDOWN within the next 12 hours. l SURVEILLANCE REQUIREMENTS' l l 4.7.1.3.1 The No. 12 condensate storage tank shall be demonstrated + OPERABLE at least once per 12 hours by verifying the contained water volume is within its limits when the tank is the supply source for the [ auxiliary feedwater pumps. 1 4.7.1.3.2 The No. 11 condensate storage tank shall be demonstrated OPERABLE at least once per 12 hours by verifying that the tank contains i a minimum of'150,000 gallons of water and by verifying that the flow path for taking suction from this tank is OPERABLE with the manual i valves in this flow path open whenever the No.11 condensate storage l l tank is the supply source for the auxiliary feedwater pumps. i l CALVERT CLIFFS-UNIT 1 3/4 7-6 CALVERT CLIFFS - UNIT 2 . -. ~. ..}}