ML19351A041

Amends 55 & 38 to Licenses DPR-53 & DPR-69,respectively, Incorporating Decay Heat Removal Capacity Requirements & Making Corrections to Both Units to Make Units Consistent

ML19351A041
Person / Time
Site:	Calvert Cliffs
Issue date:	06/16/1981
From:	Clark R Office of Nuclear Reactor Regulation
To:
Shared Package
ML19351A042	List: ML19351A041 ML19351A043
References
NUDOCS 8106250088
Download: ML19351A041 (97)

Text

{{#Wiki_filter:*p rer UNITED STATES ,,og 2 ( NUCLEAR REGULATORY COMMISSION kg '[da. <- U I WASHINGTON,0. C. 20555 'f wQ p pe BALTIMORE GAS AND ELECTRIC COMPANY J '00CKET NO. 50-317 CALVERT CLIFFS NUCLEAR' POWER PLANT UNIT NO. I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 55 License No. DPR-53 1. The Nuclear Regulatory Commis'sion (the Commission) has found that: A. The application for amer.dment by Baltimore Gas & Electric . Company (the licensee) dated January 8,1981, and corrective information provided by-letters dated February 5, March 24 and April 9,1981, 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, th6,orovisions of the Act, and the rules and regulations of the Comission; ~ C. There is reasonable assurance (i) that the activities authorized Ny this amendment can be conducted without endangering the health and safety of the public, and (ii) that sucn 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 Comission's regulations and all applicable requirements have been satisfied. l 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: (2) Technical Specifications The Technical Specifications containe.i in Appendices A and B, as revised through Amendment No. 55, are hereby incorporated i in the license. The licensee shall operate the facility in l accordance with the Technical Specifications. l 8106250088 i

f , w-1. 4 g s. .i f..--- -3l This; license. amendment is effective o~n Jnly'1,1981. 4 FOR TiiE NUCLEAR Rt!GULATORY COPJiISSION ~ ~ o h1 ' Operating Reactors Branch #3 = ' Division of Licensing.

Attachment:

Changes to'the: Technical Specifications Date 'o f. Issuance: ~ June 16, 1981 e e e b E' [ L e h,' f-s l l t. [ . - -. ~. _..,.

ATTACHMENT TO LICENSE AMENDMENT NOS. 55 AND 19 FACILITY OPERATING LICENSE NOS. OPR-53 AND OPR-69 00CKET NOS. 50-317 AND 50-318 Raplace the' following pages of the Appendix A Technical Specifications for both units with the enclosed pages as indicated. 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 completeness. Pages Pages IV 3/4 4-2a (new page) VIII' (separate pages) 3/4 4-2b (new page)' IX 3/4 5-1 X 3/4 5-2 XIII 3/4 5-7 2-12 (for clarity.), 3/4 7-26 2-13 3/4 7-45 (Unit 2 only) 2-14 (remove) 3/4 7-46 (Unit 2 only) 2-15 3/4 7-51 (Unit 1 only) 2-16 3/4 7-52 (Unit 1 only) 2-17 3/4 7-53 (Unit 2 only) 2-18 3/4 7-62 (Unit 1 only) 2-19 . 3/4 9-8 3/4 1-3 3/4.9-8a (new page) 3/4 1-16 3/4 10-2 3/4 1-23 B 3f,4 1-2 3/4 2-8 (printing error.) B 3/4 2-2 3/4 2-13 8 3/4 4-1 3/4 4-1 B 3/4 9-2 3/4 4-2 5-4 A w 1r' y 4 g'= y* --- i PTy-w w, - -y e- -ww+ tmv-1 er-- ,vwv w-T-~ -'-wy-----3 g'---

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.0 APPLICABILITY........................................... 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 B0 RATION CONTROL Shutdown Margin - T > 200 F....................... 3/4 1-1 avg Shutdown Margin - T i 200*F....................... 3/4 1-3 avg Boron Dilution...................................... 3/4 1-4 Moderator Tempera ture Coefficient................... 3/4 1-5 Minimum Temperature fo r Cri tical i ty.................. 3/4 1-7 3/4.1.2 B0 RATION SYSTEMS Flow Paths - Shutdown........................ ....... 3/4 1-8 Fl ow Pa ths - Opera ti ng............................... 3/4 1-9 Charging Pump - Shutdown............................. 3/4 1-10 Charging Pumps - Operating........................... 3/4 1-11 Boric Acid Pumps - Shutdown.......................... 3/4 1-12 Boric Acid Pumps - Operating......................... 3/4 1-13

• Borated Water Sources - Shutdown.....................

3/4 1-14 Borated Water Sources - Operating.................... 3/4 1-16 3/4.1.3 MOVABLE CONTROL ASSEMBLIES 2 Full Length CEA Position............................. 3/4 1-17 Posi tion Indicator Channel s.......................... 3/4 1-21 CEA Drop Time........................................ 3/4 1-23 Shutdown CEA Insertion Limits........................ 3/4 1-24 Regulating CEA Insertion Limits...................... 3/4 1-25 CALVERT CLIFFS - UNIT 1 III Amendment No. 32 CALVERT CLIFFS - UNIT 2 Amendment No. 18

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 LINEAR HEAT RATE........................................ 3/4 2-1 '3/4.2.2 TOTAL PLANAR RADIAL PEAKING FACTOR...................... 3/4 2-6 3/4.2.3 TOTAL INTEGRATED RADI AL PEAKING FACTOR.................. 3/4 2-9 3/4.2.4 AZIMUTHAL POWER TILT.................................... 3/4 2-12 3/4.2.5 D N B PARAM E T ER S.......................................... 3 / 4 2 - 1 3 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION...................... 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM IN STRUM E NTAT ION....................................... 3/ 4 3-10 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation.................... 3/4 3-25 Incore Detectors........................................ 3/4 3-29 Sei smic In strumenta tion................................. 3/4 3-31 Meteorological Instrumentation......................... 3/4 3-34 Remote Shutdown Instrumentation......................... 3/4 3-37 Post-Accident Instrumentation........................... 3/4 3-40 Fire Detection Instrumentation.......................... 3/4 3-43 3/4.4 REACTOR COOLANT SYSTEM 3/4:4.1 d00LANT LOOPS AND COOLANT CIRCULATION................... 3/4 4-1 S ta rt u p a n d Powe r....................................... 3/ 4 4-1 Hot Standby............................................. 3/4 4-2 Shutdown................................................ 3/4 4-2a 3/4.4.2 SAFETY VALVES........................................... 3/4 4-3 3/4.4.3 R EL I E F VALV ES........................................... 3/ 4 4-4 CALVERT CLIFFS - UNIT 1 IV Amendment No. 39, 53, 55 CALVERT CLIFFS - UNIT 2 Amendment No. JB, 36, 38 ,w~ -.r y

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION...... 3/4 7-13 3/4.7.3 COMPONENT COOLING WATER SYSTEM....................... 3/4 7-14 3/4.7.4 SERVICE WATER SYSTEM................................. 3/4 7-15 3/4.7.5 SALT WATER SYSTEM.................................... 3/4 7-16 3/4.7.6 CONTROL ROOM ~ EMERGENCY VENTILATION SYSTEM........... 3/4 7-17' ~ 3/4.7.7 ECCS PUMP ROOM EXHAUST AIR FILTRATION SYSTEM......... 3/ 4 21 3/4.7.8 HYDRAULIC SNUBBERS................................... 3/4 7-25 3/4.7.9-SEALED SOURCE CONTAMINATION.......................... 3/4 7-63 3/4.7.10 WAT ER TI GHT 0 00 RS..................................... 3/4 7-65 3/4.7.11 FIRE SUPPRESSION SYSTEMS Fi re Suppres s ion Wa ter Syst em........................ 3/4 7-66 Spray a nd/o r Sp ri nkl er Syst ems....................... 3/4 7-70 Halon System......................................... 3/4 7-72 Fire Hose Stations................................... 3/4 7-73 3/4.7.12 PENETRATION FIRE BARRIERS..............'.............. 3/4 7-75 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES 0 p e ra t i n g............................................. 3/4 8-1 Shutdown.............................................. 3/4 8-5 J ( 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Distribution - Operating......................... 3/4 8-6 A.C.' Distribution - Shutdown.......................... 3/4 8-7 i D.C. Distribution - Operating......................... 3/48-8 D.C. Distribution - Shutdown.......................... 3/4 8-11 l CALVERT CLIFFS - UNIT 1 VII Amendment No. 26 I ~

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION.................................. 3/4 9-1 3/4.9.2 ' INSTRUMENTATION...................................... 3/4 9-2 3/4.9.3 DECAY TIME........................................... 3/4 9-3 3/4.9.4 CONTAINMENT PENETRATIONS............................. 3/4 9-4 3/4.9.5 COMMUNICATIONS....................................... 3/49-5 3/4.9.6' REFUELING MACHINE OPERABILITY........................ 3/49-6 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING...... 3/4 9-7 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION............ 3/49-8 l 3/4.9.9 CONTAINMENT PURGE VALVE ISOLATION SYSTEM............ 3/49-9 3/4.9.10 WATER LEVEL - REACTOR VESSEL......................... 3/4 9-10 3/4.9.11 S P ENT FU EL POOL WAT ER L EV EL.......................... 3/4 9-11 3/4.9.12 SPENT FUEL POOL VENTILATION SYSTEM................... 3/4 9-12 3/4.9.13 SPENT FUEL CASK HANDLING CRANE........ .............. 3/4 9-16 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN...................................... 3/4 10-1 3/4.10.2 MODERATOR TEMPERATURE COEFFICIENT, CEA INSERTION AND POWER DISTRIBUTION LIMITS..................... 3/4 10-2 3/4.-10.3 NO FLOW TESTS........................................ 3/4 10-3 3/4.10.4 CENTER CEA MISALIGNMENT.............................. 3/4 10-4 3/4.10.5 COOLANT CIRCULATION.................................. 3/4 10-5 CALVERT CLIFFS - UNIT 1 VIII Amendment No. fl>' 55

4 P N INDEX BASES SECTION PAGE 3/4.0 APPLICABILITY.............................................. B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 B0 RATION CONTROL......................................... B 3/4 1-1 3/ 4.1. 2. BORATION S YST EMS......................................... B 3/4 1 -2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES............................... B 3/4 1-3 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 LINEAR HEAT RATE......................................... B 3/4 2-1 3/4.2.2, 3/4.2.3, and 3/4.2.4 TOTAL PLANAR AND INTEGRATED T T AND AZIMUTHAL RADIAL PEAKING FACTORS - F q.........75.ANDF POWER TILT - T ........................... B 3/4 2-1 3/4.2.5 -DNB PARAMETERS........................,................... B 3/4 2-2 3/4.3 INSTRUMENTATION 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURES INSTRUMENTATION'............................... B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION................................ B 3/4 3-1 CALVERT CLIFFS - UNIT 1 IX Amendment No. 27, 55 CALVERT CLIFFS - UNIT 2 Amendment No. 9, 38 ~

U INDEX BASES SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION............... 'B 3/4 4-1 3/4,4.2 SAFETY VALVES........................................ B 3/4 4-1 3/4.4.3 RELIEF VALVES....................................... B 3/4 4-2 3/4.4.4 PRESSURIZER......................................... B 3/4 4-2 3/4.4.5 STEAM GENERATORS.................................... B 3/4 4-2 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE...................... B 3/4 4-3 3/4.4.7 CHEMISTRY........................................... B 3/4 4-4 3/4.4.8 SPECIFIC ACTIVITY................................... B 3/4 4-4 3/4.4.9 PRESSURE / TEMPERATURE LIMITS......................... B 3/4 4-5 3/4.4.10 STRUCTURAL INTEGRITY................................ B 3/4 4-12 3/4.4.11 CORE BARREL MOVEMENT..............,................. B 3/4 4-12 3/4.4.12 LETDOWN LINE EXCESS FLOW............................ B 3/4 4-12 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 SAFETY INJECTION TANKS.............................. B 3/4 5-1 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS........................ B 3/4 5-1 3/4'.5.4 R E FU EL I N G WAT E R TAN K ( RWT ).......................... B 3/4 5-2 CALVERT CLIFFS - UNIT 1 Amendment No. 57,55 CALVERT CLIFFS - UNIT 2 X Amendment No. 6, 39, 38 O +- r F 4* ~ y-w--= y r y-p ,e n ,.+.wy

.INDEX BASES SECTION PA'GE 3/4.9.5 COMMUNICATIONS........................................ B 3/4 9-1 3/4.9.6 REFUELING MACHINE OPERABILITY......................... B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING............ B 3/4 9-2 5 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION............. B 3/4 9 2 3/4.9.9 CONTAINMENT PURGE VALVE ISOLATION SYSTEM............. B 3/4 9-2 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL AND SFENT FUEL P0OL WATER LEVEL........................ B 3/4 9-3 3/4.9.12 SPENT FUEL POOL VENTILATION SYSTEM................... B 3/4 9-3 3/4.9.13 SPENT FUEL CASK HANDLING CRANE....................... B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN-MARGIN......................s.............. B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS............................................. B 3/4 10-1 3/4.10.3 NO FLOW TESTS........................................ B 3/410-1 3/4.10.4 CENTER CEA MISALIGNMENT.............................. B 3/410-1 3/s.10.5 ' COOLANT CIRCULATION................................. B 3/4 10-1 CALVERT CLIFFS - UNIT 1 Amendment No. 26, 55 CALVERT CLIFFS - UNIT 2 XIII Amendment No. 6, 77, 38 ,n a,, -e --,,------n,-- e-

---

.-----...e,,

,-w, g,-+--

INDEX DESIGN FEATURES' SECTION PAGE 5.1 -SITE E x c l u s i o n A r ea............................................ 5-1 Low Po pu l a ti o n Zo ne....................................... 5-1 5.2 CONTAINMENT Co n f i g u ra t i on............................................. 5-1 Des ign Pressure a nd Tempera ture........................... 5-4 5.3 REACTOR CORE ' Fuel Assemblies........................................... 3-4 Control El emen t As s embl i es................................ 5-4 5.4 i.EACTOR COOLANT-SYSTEM Design Pressu re a nd Tempera tu re.....'........".'............. 5-4 1: Vo1ume.................................................... 5-5 5.5 METEOROLOGICAL TOWER LOCATION............................. 5-5 [ FUEL STORAGE 5.6 i Criticality............................................... E-5 j ' Drainage.................................................. 5-5 t C a p a c i ty.................................................. 5-5 5.7 COMPONENT CYCLIC OR TRANSIENT LIMITS...................... 5-5 1 [~ CALVERT CLIFFS - UNIT 1 XIV CALVERT CLIFFS - UNIT 2 e L

1.30 UNACCEPTABLE -.

• (0,1.25)

UNACCEPTA BLE 5-OPERATION OPERATION .e REGION /4 REGION EE

__l--\\

1. 2 0 - - -.--, - --

j \\ .w 3--.. - \\.. ._. __.. =_. f , i_. t 'I .= /.- .y_ _ ; --- m 1.10 - - - ,f-- -x-----------= w 3: O .- -/ \\. a,, s l

• 2 3

.00 _ (.2,1.00) EI ---5 (+. 2, 1. 00) '-~~ ~ 1 -r 1-mx _3. -. _-g_ n -.\\_... g . -.. -. = - / y=-

i--===- =Z

• 0. 90 ~~=.

r,' ~- u_ o l Z /- i O m H ^ ~-_\\_ _D}_ZN.l.i.- O n. i I < n.on - /

• - _.\\=

v. ?U. g ACCEPTA BLE .._.c=- - ;- (-0.4, 0.75)7(/ Og{0N 'M(0.4,.75T u- = 0.7.0 .a 0.60 - -0.6 -0.4 -0.2 0 0.2 0.4 0.6 PERIPHERAL AXIAL SHAPE INDEX, Y-1 Figure 2.2-1 1 U PERIPHERAL AXIAL SHAPE INDEX, Y VS FRACTION .6 j. g OF RATED THERfML POWER CALVERT CLIFFS - UNIT 1 Amendment No. 27, ZA,48 CALVt.RT CLIFFS - Ur.IT 2 2-11 Amendment No. 3,31

n n.

p 3 rr mm

u :o 1.5 l-

'6 a l i 2._ nn 4 i. 3.. 13.'. d: 8 l .i~

!.. i

-l e rr 2 i Q]

f J ij

-l Ap0.5 ASt+1.10 - -*l-h -1

g--

I-

+- l

I:

j 'f l - i !. I': i:8 i

• - * ~

g,4 + _y ...L -P - ---l : 5 -t-i--l--. i p. Mm .{ j. _. r-- i l. ' l.. ._.l.. \\.t _.._!.. + '. _ t.. _..L'. t. j ..i.i ,..8 l...,... _ _ {"- - ~i.._.. h _E fi 8 8 ...{ ' I 'j cc g g 7 p l 1 i u i . -. ~ . l.; l. [....i.. .g j;. 3g -+-(-- - + - ---t-- ^

• Ag=+0.5 ASl+0.90.,;,

a. ~ 1.3 4-g. ' g' rv - l....,

l ' e~

i .3

p. k p

I t-. .4 ii._. "_ .m r~ .:.. : h t.C .l. d,. ' '.. l ! al.il l i' ~' ".dm ..f.* - i "i (i .I \\ te.2.1.20) +'- q d' .i; ..l. l ". ' ~ A 1.2 - r - -- r-7 j - g h. - m--- ..gi.. al.M 'b i- -a aq.. ... j... .]...Q fi;? .a i-r i y; ..l.

..j.

. l.. .j. .. f.. ....._h: e. .; ;.a.[ ...i _..;.j _....C.. ._ 4 pl:. . l? J. .j i e -l t. g ro g. .] i.: l ..:. ii.... : u.. id

l.

0. 1.500 L . j. .j. .h._

2..;._

- --{ T-- t i i t[] ODNB"#1 g i .j mOR . q. :j _;. _; 1.0 s___a '2 I' i-1 l. i(+0.2.1.000f P

• 2061(A )(OR l+15 85sT m5 e

g g IN gn s g-- .._ k. l..J.. '.. _ 4 4 I <o g 1 . j.. _ j......... _,.., l 1 T i i s i i i. i. i 0- n, l j. u. M. a I I I I I ~ l $g 0.9 s 0.5 -0.4 4.3 -0.2 0.1 0 0.1 0.2. 0.3 0.4 0.5 i et 2o ASI

• m T

7 C FIGURE 2.2-2 O Thermal Margin / Low Pressure Trip Setpoint N Part 1 (ASI Versus A ) 1 u i LO ~,Jn g 3== r= i

1 lREACTIVITYCONTROLSYSTEMS 0 200 F SHUTOOWN MASGIN=- Tavq 1 LIftITING CONDITION FOR OPERATION 3.1.1. 2 The SHUTCO'.lN MARGIN shall be > 3.0% ak/k. ll APPLICABILITY: MODE 5 a. Pressurizer level > 90 inches from bottom of the pressurizer. b.~ ' Pressurizer level < 90 inches from bottom of the pressurizer and all sources of non-borated water 188 gpm. ACTION: a. With the ;.ajTDOWN MARGIN < 3.0% ak/k, immediately initiate and continue boration at > 40 gpm of 2300 ppm boric acid solution or equivalent until ~ the required SHUT 00WN MARGIN is restored. b. With the pressurizer drained to < 90 inches and all sources of non-borated water > 88 gpm, irmediately suspend all operations involving positive reactivity changes while the SHUTDOWN MARGIN is increased to compensate for the additional sources of non-borated water or reduce the sources of non-borated water to 1 88 gpm. SURVEILLANCE REQUIREMENTS 4.1.1. 2 The SHUTD0WN MARGIN shall be determined to be > 3.0% ak/k: l a. WitFin one hour after detection of an inoperable CEA(s) and at least on'.e per 12 hours thereafter while the CEA(s) is inoperable. If the inoperable CEA is immovable or untrippable, the above required HUT 00WN l1ARGIN shall be increased by an amount at least equal tc the withdrawn worth of the immovable or untrippable CEA(s). b. At least once per 24 hours by consideration of the following factors: 1. . Reactor coolant system boron concentration, 2. CEA position, 3. Reactor coolant system average temperature, 4. Fuel burnup based on gross thermal energy generation, 5. Xenon concentration, and 6. Samarium concentration. 4.1.1. 2. 2. With the pressurizer drained to 1 90 inches determine: a. Within one hour and every 12 hours thereafter that the level in the reactor coolant system is above the bottom of the hot leg.qoz:les, and b. Within one hour and every 12 hours thereafter that the sources of non-borated water are 1 88 gpm or the shutdown margin has compensated for the additional sources. CALVERT CLIFFS - UNIT 1 3/4 1-3 Amendment No. A8, 55 CALVERT CLIFFS - UNIT 2 Amendment No. 31

REACTIVITY CONTROL SYSTEMS B0RON DILUTION LIMITING CONDITION FOR OPERATION 3.1.1.3. The flow rate of reactor coolant through the reactor coolant system shall be 3.3000 gpm whenever a reduction in Reactor Coolant System boron concentration is being made. APPLICABILITY: ALL MODES. ACTION:- With the flow ~ rate of reactor coolant through the reactor coolant system < 3000 gpm, immediately suspend all operations. involving a reduction in boron concentration of the Reactor Coolant System. SURVEILLANCE REQUIREMENTS 4.1.1. 3 The. flow rate of reactor coolant sii.;i3h the reactor coolant system shall be detenmined to be 3, hour during a reduction in the 3000 gpm within one hoar prior to the start of and at least cnce per Reactor Coolant System boron concentration by either: a. Verifying at least one reactor coolant pump is in operation, or b. Verifying that at least one low pressure safety injection pump ,is in operation and supplying 3. 3000 gpm through the reactor coolant system. e 9 CALVERT CLIFFS-UNIT 1 i CALVERT CLIFFS-UNIT 2 3/4 1-4 l

170 .i.. t, ..l {,

=i"_^ iri:' "fii'i:__

. E-i2 -i-- ~f-i:: y ' :.. '.. - _ i ::!.a.Z. - =. j..

r.

+f. :

n.t.

n..=.. 130

r...

_:=..=:.=...

I U .} t 5!:YDI 55 2dI5t:-5i5l~ E'5 Miin ' Di-t :=i ' l' I-~ ES U T k'. ........~ i-~ 23! 2 i;51..ir.......E Uii :-. _...r= . d.. :-E, ida - -*!! i.r. = t i" ~ ui6..a_. ' 120 _.i.___ =._.}=_=._=..f:_=.r. _ =._=... f=.,....1._=.. .:=_....2..___. _.. _. 4, _ .:.._...._..._.f.:_....=.:_r.... tx. r

:::. =;

u. .:n-n r. -. a _ l : d ;. - - - - -. =--=

us:n

r'l = : - --. : t.= :

m = =. _ -

'k.5!"i 5:5E 255}i:Ns 5-die M l"

==-tr: J} -- --r-- $g i-- 5 55 ;-!:'- =El 6 f.5Y 3 9iEE;_' iCT

1. ii-M id-5 ti -r M Tzi'

- -@ili: ~ l 2 2 HME=M-4:!ME===iME=f=i=1 N=Ps.1 W "!If i=i'" ~ W E T=_.?i=~ t=iN=_5==3=%= &i.- += *t-i= 5%= =i% Elm =M ? .i = w 110 .v..___,_ _.a;; _2 cm .,= I.m.== ..t;; ,,n tm, ___a x _ 4 1

n

.r::. t

- r---n :

r-- - c.r-- - W _:_ _,..;...-._ ~_.... :.b. _r-Y-...

--- :-?

-- t. g ^' C ^ ~5 ~ ~I =_ E-I..... ~ ^ h =_...L: t = li =. _N ~_~.~ w M .=-i-. _ _.h_.- G. .T. = 100 g =- = =f..:._ - s ~ ~ ~ ' ' ~ - 'f_ =- _..=... _... _ _ _ --!= _....: r_l=_=__===d=.::=. :.::.:. = r_ T: _=4 = z .= t r.: : 2.

== r:; - t--- w 4 ~~~:J_. y...... .._ t== a ---

. a. y.=... {>.=.. p _

g

== : 90 ~ ~ - - ~ ~ + M O. D E.S 1, 2. 3, & 4_F_-1.:~_ Wn .. =.. _ -. .. f =.. r.: _..: : - . :- r._=.- ri. g u ! = 0 f != : '-iii." : 5 =E 2.: "" := [- Fi r-H

i;"l_.. =. _.

a . = = _ r -_,_.:_=.. .. +:_= = === =2

. :==:== :- = -

= u===. _: y..=a... .. m= MiT.--_l5L'E "_;dJ.b}:-c g =: -- 2. t-5 '- (=h cfi*f:E"r3fli55'_- i =r:;: i:gyg /., _m... _= o 70 .. =. 2 N. -. _ y w -- ._n--- 2. 2.-. ,,_T c. =_. =.:: : - =.=.g._._..__. . =..... u: _ .. :r 4 80 ,o,,, .__.. _ _ _ _ -....__.p._.._.._.,_;_.. _ _ _ _ g.._ _ _._ _..... _g_.. _ _ _p.. g r___. O . : =.

.:-. __ f._. = _-..r. a..:.r.e _.--.

+ - _.. e: z.: g -_7. _---j. r_ =.. =.. -_-- = _:=...: ,.y_._..._. ........,5.=_,... ~ - ...n. .::.__.4,_=_l.__.__..._.._............ _. _.... _.. _....., _. }. ~.r. __ _.. . _. _....._..p 4r.. g g _ -i _-,_rix :* ~2 +. : T - E r9;MI.1 f-=

~ :

rr E

. _ _ ____:-._-;_=... _=_ ! =. :;_---- =..1._. _ _ _ _ _..p___. g ._ r,at,,_ t.,__...__ _, _ _ t_ . _. n._ __._.3...r-=..--t-- r-- :-- - - -- r _ ' ~ =" ~ ' " #~d',";. m _. _., e 2 20. = = = = ="=~...t==- "**'".=:--- - ~ " ~ ' ~ ~ ~ ~ "" #~ =_y====.--,_==.l=======a _ ' ='u-~..au:. h.'=-.:.

==_2 = = = :. =_r -- -- .= u-7 = = a. u r_ _i__.=____=_-:cu=== =_; =a ;.n.c=r.: . - - * " * " _ - ' 7 t !-*. ^ -. ;=.=__ _;.=*_ 2 =._ ..u; l ""I-*._s,.;=-* f. l _ ~--. =;. =--- __=..r=,a _ = r= =E:_- = -- :_= =- 1 - ::=. = :=._..:.;f._. =.. -- - :- nu== - =:

===== :_

==. t

-- t. _....

i.-... _ _ _d.._

_._ =r, _. _-_ _=_=.r : r_ r.. _ _ _ _ _.._ _.r.. 10 te. = l

---

 ; p q:---

,1=;= :.: " MOD ES 5 & 6 F u = x.c. 4 = = = ra. :=. . :== - _2= : c=. . k:=_a.;- - -r - . -- : -l _. : 'I e _ =. u_

== n- - =:_ L _ _ _I:=- = =2 __ _=_ =.=: _=- I --... _ = =.... =: 2E=u;; ;-_.I~_=: __... : :.. h...... L... __== - r-i= : .._.._a]._. ......_g_._. .__""!_.._.:4,2 4..: ....J.__!*._.. ....4_ 6 7 8 9 10 11 12 STORED BORIC ACID CONCENTRATION (WT%) FIGURE 3.11 Minimum Boric Acid Storage Tank Volume and Temperature as a Function of Stored Boric Acid Concentration l l CALVERT CLIFFS - UNIT 1 Amendment No. 27, 48 CALVERT CLIFFS - UNIT 2 3/4 1-15 Amendment No. E, 31 P00RBR3M

REACTIVITY' CONTROL SYSTEMS BORATED WATER SOURCES - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.8 At least two of the following three borated water sources shall be OPERABLE: a. Two boric acid storage tank (s) and one associated heat tracing circuit per tank with the contents of the tanks in accordance with Figure 3.1-1 and the boron concentration limited to < 8%, and b. The refueling water tank with: 1. A minimum contained borated water volume of 400,000

gallons, 2.

A beron concentration of betwsen 2300 and 2700 ppm, l 3. A minimum solution temperature of 40'F, and 4. A maximum solution temperature of 100*F in MODE 1. APPLICABIL ITY: ~ MODES 1, 2, 3 and 4. ACTION: With only one borated water source OPERABLE, restore at least two borated water sources to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours and borated to a SHUTOOWN MARGIN equivalent to at least 3% ak/k at 200*F; restore at least two borated water sources to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours. SURVEILLANCE REQUIREMENTS 4.1.2.8 At least two borated water sources shall be demonstrated OPERABLE: a. At least once per 7 days by: l 1. Verifying the baron concentration in each water source, I l 2. Verifying'the contained borated water volume in each watar source, and l 3. Verifying the boric acid storage tank solution temperature. l b. At least once per 24 hours by verifying the RWT temperature l when the outside air temperature is < 40 F. Amendment No. 48, 55 CALVERT CLIFFS - UNIT 1 3/4 1-16 CALVERT CLIFFS - UNIT 2 Amendment No. 31, 38 I - ' 'l

O REACTIVITY, CONTROL SYSTEMS CEA DROP TIME LIMITING CONDITION FOR OPERATION 3.1.3.4 The individual full length (shutdown and control) CEA Jrop time, from a fully withdrawn oosition, shall be 1 3.1 seconds from when the ll electrical-powe-is interrupted to the CEA drive mechanism until the CEA reaches its 90 percent insertion position with: a. .T > 515*F, ar.d avg b. All reactor coolant pumps operating. APPLICABILITY: MODES 1 and 2. ACTION: a. With the drop time of any full length CEA determined to exceed the above limit, restore the CEA drop time to within the above limit prior to proceeding to MODE 1 or 2. 'b. With the CEA drop times within limits but determined at less than full reactor coolant flow, operation may proceed provided THERMAL POWER is restricted to less than or equal to the maximum THERMAL POWER level allowable for the reactor coolant pump combination operating at the time'of CEA drop time determination. SURVEILLANCE REQUIREMENTS 4.1.3.4,The CEA drop time of full length CEAs shall be demonstrated through measurement prior to reactor criticality: a. For all CEAs following each removal of the. reactor vessel head, b. For specifically affected individual CEAs following any main-tenance cn or modification to the CEA drive system which could affect the drop time of those specific CEAs, and c. At least once per 18 months. CALVERT CLIFFS - UNIT 1 3/4 1-23 Amendment No. 32, 39, 55 CALVERT CLIFFS - UNIT 2 Amendment No. 76, 78, 38 w y-7 ,-s-a p g + - -e9, eiy y .-9 +rw-y ,w gpw- ~wwyT-v,--- w -y,

l REACTIVITY dONTROL SYSTEMS. -SHUTOOWN CEA INSERTION LIMIT LIMITING CONDITION FOR OPERATION 3.1.3.5 All shutdown CEAs shall be withdrawn to'at least 129.0 inches. l APPLICABILITY: MODES 1 and 2*#. ACTIO1: Wi'.h a maximum of one shutdown CEA withdrawn, except 'for surveillance testing pursuant to Specification 4.1.3.1.0, to less than 129.0 inches, l-within one hour either: a. Withdraw the CEA to at least 129.0 inches, or l b. D:clare the CEA inoptrable and apply Specification 3.1.3.1. SURVEILLANCE REQUIREMENTS 4.1.3.5 Each shutdown CEA shall be determined to be withdrawn to at I least 121.0 inches: a. Within 15 minute 1 prior to withdrawal of any CEAs in regulat-ing groups during an approach to reactor criticality, and' , b. ,At least once per 12 hours thereafter.

• See Special Test Exception 3.10.2.

1. With K,ff 1.0 3,

CALVERT CLIFFS-UNIT 1 Amendment No. 28 CALVERT CLIFFS-UNIT 2 3/4 1-24 Amendment No.13 .._7_,_ ..,,-,7-, r-m. ,--m., _,..,,.,,, ~,.,,,., ,_.,_m....

4 POWER' DISTR'I3UTION ' LIMITS - SURVEILLANCE REQUIREMENTS (Continued) shall'bedeterminedeachtimeacalculationofFfy 4.2.2.3 F is required xy by using the incore. detectors to obtain a power distribution map with all full _ length CEAs at or above the Long Term Steady State Insertion Limit for the existing Reactor Coolant Pump combination..This determina-tion shall be limited to core planes between 15% and 85% of full core height inclusive and shall exclude regions influenced by grid effects. 4.2.2.4 T shall be determined each time a calculation of F, is required q and the value of T used to determine F shall be the measured value of q xy q. ~ a CALVERT CLIFFS-UNI' 1 Amendment No. 27, 32 CALVERT CLIFFS-UNIT 2 3/42-7 Amendment No. 9., 18 ,_q ,--,-r. yv-x-,--y- -m-e-v4 e r-v--= - - - - - -r--- +--=--'w+-**e v w s'"1 W~ v'

• • -T'-v'

ll Ill lllllllllllIIIIllllll T EE 1'00' 11.62, 1.00) UNACCEPTABLE if, i?, OPERATION qq se J' REGION '9 fittilittlittilittliittititil ny!q ,Q s i !,j ,.Fhy LIMIT CURVE 2 0.90 6' ' IIi t T ,y, F LIMIT CURVE ss s r '['l y 7(1.70,.85) "' s .,, s s a s le U.80 s. 4'" (1.695,.775)' .I u. o C> ACCEPTABLE ,2, OPERATION 0.70 REGION 1 c; -i. t i ld ts_ '_' l 0.60 1; e i

E it F,

4 M8 __j .?. ti i? Q En gg g U.50 I lll 1. u Cl3 1.56 1.58 1.60 1.62 1.64 1.66 1.68 1.70 1.72 WM Cl3 T T g FXY > f r M &; Figure 3.2-3 l TOTAL RADIAL PEAKlHG FACTORS vs ALLOWABLE FRACTION OF RATED TilERMAL POWER 2:= m

POWER.DISTRJBUTION LIMITS DNS PARAMETERS LIMITING CONDITION ~ FOR OPERATION 3.2.5 The following DNB related. parameters shall be maintained within the limits shown on Table 3.2-1: a. Cold Leg Temperature-b. Pressurizer Pressure c.- ' Reactor Coolant. System Total Flow Rate ~ d. AXIAL-SHAPE INDEX APPLICABILITY: MODE 1. ACTION: With any of the above parameters exceeding 'its limit, restore the parameter to within its limit within 2 hours or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 4 hours. SURVEILLANCE REQUIREMENTS 3 ~ 4.2.5.1 Each of the parameters of Table 3.2-1 shall be verified to be within their limits at least once per 12 hours. 4.2.5.2 The Reactor Coolant System total' flow rate shall be determined to'be within its limit by measurement at least once per 18 months. a CALVERT CLIFFS-UNIT 1 Amendment No. 39,1855 Amendm'at No. 9, CALVERTLCLIFFS-UNIT 2 3/4 2-13 - ~ .,y., ,.,f.,,.c,, ..,_,,,,,,,,m..,.w,, ,,_,,,,,y_,.., _m_,m,..,,,.,,-.. ,~.9

. TABLE 3.2-1 o :. (( DNB PARAMETERS 90 --e -4 pp LIMITS 44 Four Reactor Three Reactor Two Reactor Two Reactor TY Coolant Pumps Coolant Pumps Coolant Pumps Coolant Pumps EE Parameter Operating .0perating Operating-Same Loop. Operating-Opposite Loop i Cold Leg Temperature 1 548 F m-Pressurizer Pressure > 2225 psia

• l Reactor Coolant System

{ Total Flow Rate > 370,000 gpm 2 AXIAL SHAPE INDEX Figure 3.2-4 M I

• Limit not applicable during either a THERMAL POWER ramp increase in excess of 5% of RATED THERMAL POWER j

per minute or a THERMAL POWER step increase of greater than 10% of RATED THERMAL POWER. l

• • These values left blank pending NRC approval of ECCS analyses for operation with less than four reactor coolant pumps operating. !

EN I a&& 8; nn oO j . E$ "o l I 4 e a m

3/4.4

• REACTOR COOLANT SYSTEM COOLANT LOOPS AND COOLANT CIRCULATION STARTUP AND POWER OPEkaTION~

LIMITING CONDITION FOR OP'ERATION 3.'4.1.1 Both reactor coolant loops and both reactor coolant pumps in each loop shall be in operation. APPLICABILITY: MODES -1 and 2*. ACTION: With less than'the above required reactor coolant pumps in operation, be in at least HOT STANDBY within 1 hour. SURVEILLANCE REQUIREMENTS 4.4.1;l The above required reactor coolant loops shall be verified to be in operation and circulating reactor coolant at least once per 12 hours. ~ J

• See Special Test Exception 3.10.3.

CALVERT CLIFFS - DNIT 1 ar.andment No. 55 CALVERT CLIFFS ' UNIT 2 3/4 4-1 Anendment No. 38

REACTOR COOLANT SYSTEM COOLANT LOOPS AND COOLANT-CIRCULATION HOT STANDBY-LIMITING CONDI1101 FOR OPERATION 3.4.1. 2 ' a. The reactor coolant loops listed'below shall be OPERABLE: 1. . Reactor Coolant Loop #11 (#21) and at least one. associated reactor coolant pump. 2. Reactor Coolant Loop #12 (#22) and at least one associated reactor coolant pump. b. At least one of the above Reactor Coolant Loops shall be in operation *. APPLICABILITY: MODE 3 ACTION: .a. With less than the above required reactor coolant loops OPERABLE, restore the required loops to OPERABLE status within 72 hours or be.in HOT SHUT 00WN within the next 12 hours. b. With no reactor' coolant loop in operation, suspend all operations involving a reduction in boron concentration E of-the. Reactor Coolant System and initiate corrective action to return the required' loop,tp operation within one hour. SURVEILLANCE REQUIREMENTS

4. 4.1. 2.1 At least the above required reactor coolant pumps, if not in operation, shall be determined to be OPERABLE once per 7 days by verifying correct breaker alignmer:s and indicated power availability.

4.4.1.2.2 ' At least one cooling loop shall be verified to be in operation and circulating reactor coolant at least once per 12 hours.

• All reactor coolant pumps may be de-energizec for up to 1 hour (up to 2 hours for low flow test) provided (1) no operations are permitted that would cause dilution of uhe reactor coolant system boron cogcentration, and (2)' core outlet temperature is maintained at least 10 F below saturation temperature.

CALVERT CLIFFS - UNIT 1 Amendment No. AB, 55 CALVERT CLIFFS - UNIT 2 3/4 4-2 Amendment No. 31, 38 s -*e s--*t 4+-7-^-' M NP +- w 9 ? <-7+'=mt -t'- 'F-T-P"'t P-w44-- V T V 1

• - 7 T

T*+9-'

REACTOR COOLANT SYSTEM = COOLANT LOOPS AND C0_0LANT CIRCULATION SHUTDOWN LIMITING CONDITION FOR OPERATION P 3.4.1.3 a. At-least two of the coolar.t loops listed below shall be 0PERABLE: 1. Reactor Coolant Loop #11 (#21) and 'its associated steam generator and at least one associated reactor coolant pump, 2. Reactor _ Coolant Loop #12 (#22) and its associated steam generator and at least one associated reactor coolant pump. 3. Shutdown Cooling Loop #11 (#21)*, 4. Shutdown Cooling Loop #12 (#22)*. b. At least one of the above coolant loops shall be in operation **. APPLICABILITY: MODES 4***# and 5***#. ACTION: a. With less than the above required coolant loops OPERABLE, initiate corrective action to return the required coolant loops to OPERABLE status within one hour or be in COLD SHUTDOWN within 24 hours. b. With no coolant loop in operation, s'u' spend'all operations involving a reduction in boron concentration of the Reactor Coolant System and initiate corrective action to return the required coolant loop _to operation within one hour. SURVEILLANCE REQUIREMENTS

4. 4.,1. 3.1 determined,The required shutdown cooling loop (s), if not in operation, shall be OPERABLE once per 7 days by verifying correct breaker alignments and indicated power availability for pumps and shutdown cooling loop valves.

• The normal or emergency power source may be inoperable in MODE 5.
  • All reactor coolant pumps and shutdown cooling pumps may be de-energized for up to 1 hour provided (1) no operations are permitted that would cause dilution of the reactor' coolant system boron concentration, and (2) core l

outlet temperature is maintained at least 10 F below saturation temperature. 0 l. ~ ***A reactor coolant pump shall not be started with one or more of the RCS l cold _ leg temperatures less than or cqual to 275 F unless (1) the pressurizer water volume is less than 600 cubic feet or f 2) thg secondary water tempera-ture of each steam generator is less than 46 F (34 F when measured by a surface contact instrument) above each of the RCS cold leg temperatures.

1. See Special Test Exception 3.10.5.

l CALVERT CLIFES - UNIT 1 Amendment No. 55 CALVERT CLIFFS - UNIT 2 3/4 4-2a Amendment No. 38

4 REACTOR COOLANT SYSTEM COOLANT LOOPS AND COOLANT CIRCULATION SHUT 00WN-SURVEILLANCE REQUIREMENTS (Continued) 4.4.1.3.2' _-The required steam generator (s), if.it is being used to meet-3.4.1.3.a. shall be determined _0PERABLE by verifying the secondary side water level to be 'above--50 inches at least once per 12 hours. .4.4.1.3.3 At least one ' coolant loop shall be verified to be in. operation and circulating reactor coolant at.least' once 'per 12 hours. A CALVERT CLIFFS - UNIT 1 Amendment No. 55 CALVERT-CLIFFS - UNIT 2 3/4 4-2b Amendment No. 38 n -a .-w-- y--,--r, -., - ~, ,w,e- <--~,--,,-.,----m-nn-nr ,pg,,, e-

3/4._5' EMERGENCY CORE COOLING SYSTEMS (ECCS) SAFETY. INJECTION TANKS LIMITING CONDITION FOR OPERATION 3.5.1 Each reactor coolant system safety injection tank shall be 29cRABLE with: a. The isolation valve open, b. A contained borated water volume of between 1113 and 1179 cubic feet of borated water (equivalent to tank levels of between 187 and 199 inches, respectively), c. A boron concentration of between 2300 and 2700 ppm, and - l 'd. A nitrogen cover-pressure of between 200 and 250 psig. APPLICABILITY: MODES 1, 2 and 3.* ACTION: a. With one safety injection tank inoperable, except as a result of a closed isolation valve, restore the inoperable tank to OPERABLE status within one hour or be in HOT SHUTDOWN within the next 12 hours. b. With one safety injection tank inoperable due to the isolation valve being closed, either immediately open the isolation ~ va.ve or be in HOT STANDBY within one hour and be in H0T SHUTDOWN within the next 12 hours. SURVEILLANCE REQUIREMENTS 4.5.1 Each safety injection tank shall be demonstrated OPERABLE: a. . At least once per 12 hours by: l 1. Verifying the contained borated water volume and nitrogen cover-pressure in the tanks, and 2. Verifying that each safety injection tank isolation valve is open.

• With pressurizer pressure > 1750 psia.

CALVERT CLIFFS - UNIT 1 Amendment No. AB, 55 CALVERT CLIFFS - UNIT 2 3/4 5-1 Amendment No. 37, 38

o EMERGENCY CORE COOLING-SYSTEMS ~ SURVEILLANCE REQUIREMENTS (Continued) b. 'At least once per 31 days by verifying the boron concentration of the safety injection tank solution. c. At least once per 31 days'when the RCS pressure is above 2000 psig, by verifying that power to the isolation valve operator is removed by maintaining the feeder breaker open .under administrative control. d. Within 4 hours prior to increasing the RCS pressure above 1750 psia by verifying,;via. local-indication at the valve, that the tank isolation valve is open. At least once per 18 months by verifying that each safety e. injection tank isolation valve opens automatically under each of the following conditions: 1. When the RCS pressure exceeds 300 psia, and 2. Upon' receipt of a safety injection test signal. f. Within one hour. prior to each increase in solution volume of > 1% of normal tank volume by verifying the boron concent-ration at the operating high pressure safety injection pump discharge is between 2300 and 2700 ppm. 3 CALVERT CLIFFS - UNIT 1 3/4 5-2 Amendment No. ff, 55 CALVERT CLIFFS - UNIT 2 Amendment No. 31, 38 l L.

EMERGEhCY CORE COOLING SYSTEMS ECCS SLBSYSTEMS - T < 300 F avg LIMITING CONDITION FOR OPERATION i 3.5.3 As a minimum, one ECCS subsyst' em comprised of the following shall be OPERABLE: .One# OPERABLE high-pressure safety injection pump, and l a. b. An OPERABLE flow path capable of taking suction from the refueling water tank on a Safety Injection Actuation Signal and. automatically transferring suction to.the contain-ment sump on a. Recirculation Actuation Signal. APPLICABILITY: MODES 3* and 4. ACTION: a. With no ECCS subsystem OPERABLE, restore at least one ECCS subsystem to OPERABLE status within I hour or be in-COLD SHUTDOWN within the next 20 hours. b. In the event'the ECCS is actuated and injects water into the Reactor Coolant System, a Special ~ Repo,rt shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date. SURVEILLANCE REQUIREMENTS 4.5.3.1 Thi ECCS subsystem shall be demonstrated OPERABLE per the applicable l Surveillance Requirements of 4.5.2. 4.5.3.2 All high-pressure safety. injection pumps, except the above required OPERABLE pump, shall be demonstrated inoperable at least once per 12 hours whenever the temperature of one or more of the RCS cold legs 'is 1 275 F by verifying that the motor circuit breakers have been removed from their electrical power supply circuits. "With pressurizer pressure < 1750 psia.

1. A maximum of one high-pressure safety injection pump shall be OPERABLE whenever the temperature of one or more of the RCS cold legs is 1 275'F.

CALVERT CLIFFS - UNIT 1 3/4 5-6 Amendment No.34 CALVERT CLIFFS - U: LIT 2 Amendcont io.16 ~

EMERGENCY' CORE COOLING SYSTE,MS, REFUELING WATER TANK LIMITING CONDITION FOR OPERATION 3.5.4 The refueling water tank shall be OPERABLE with: a. A minimum contained borated water volume of 400,000 gallons, -b. - A boron con.ntration of between 2300 and 2700 ppm, l c. A minimum water temperature of 40*F, and d. A maximum solution temperature of 100*F in MODE 1. APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: With the refueling water tank inoperable, restore the tank to OPERABLE status within 1 hour or be in at least HOT STANDBY within 6 hours and in COLD SHUTDOWN within the following 30 hours. SURVEILLANCE REQUIREMENTS 4.5.4.The RWT shall be demonstrated OPERABLE: a. At least once per 7 days by: l l

1.

Verifying the contained borated water volume in the tank, and i 2. Verifying the boron concentration of the water. b. At least once per 24 hours by verifying the RWT temperature when the outside air temperature is < 40*F. l CALVERT CLIFFS - UNIT 1 3/4 5-7 Amendment No./2,55 CALVERT CLIFFS - L'dIT 2 Amend..cnt ::o. 37, 38

4 PLANT-SYSTEMS 3/4.7.8 HYDRAULIC SNUBBERS ~ LIMITING CONDITION FOR OPERATION 1 3.7.8.1 All hydraulic snubbers listed in' Table 3.7-4 shall be OPERABLE. APPLICABILITY: M00ES - 1,. 2, 3 and 4. ACTION: With 'one or.more hydraulic snubbers inoperable, replace or restore the inoperable snubber (s)- to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the fo'. lowing 30 hours. SURVEILLANCE REQUIREMENTS - 4.7.8.1. Hydraulic snubbers shall be demonstrated OPERABLE by performance of ^ the following augmented inservice inspection program and the requirements of Speci fication '4.0.5. a. Each hydraulic snubber with seal material. fabricated from ethylene propylene or other materials demonstrated compatible with the opec *,?.it.g environment and approved as such by the NRC, Eshall be detat"#..ed OPERABLE at least'once after not less than 4 months but t. thin 6 months of initial criticality and in ac-cordance.with the inspection schedule of Table _4.7-4 thereafter, by a visual inspection of the snubber. Visual inspections of the snubbers shall include, but are not necessarily limited to, in - spection of the hydraulic fluid reservoirs, fluid connections, and linkage connections to the piping'and anchors. Initiation of the Table 4.7-4 inspection schedule shall be made assuming the unit was previously at the 6 month inspection interval. b. Each hydraulic snubber with seal material not fabricated from l-ethylene propylene or other materials demonstrated compatible with the operating environment shall be determined OPERABLE at least once per 31 days by a visual inspection of the snubber. Visual inspections of the snubbers shall include, but are not necessarily limited to, inspection of the hydraulic fluid re-servoirs, fluid connections, and linkage connect'or, to the piping and anchors. CALVERT CLIFFS-UNIT 1 3/4 7-25 CALVERT CLIFFS-UNIT 2 Amendment No. 10 1

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS-(Continued) c. ' At least once per 18 months during shutdown, a representative sample of.at least 10 hydraulic snubbers or-at least 10% of all snubbers listed in Table 3.7-4, whichever is less, shall . be selected and functionally tested 'to verify correct piston movement,, lock up and bleed. Snubbers greater than 50,000 lb. capacity may be excluded from ~ functional. testing requirements. Snubbers selected for. functional testing shall be selected on a rotating basis. Snubbers identified as either "Especially ~ Difficult to Remove" or in."High Radiation Zones" may be exempted from' functional testing provided these snubbers were. demonstrated GrERABLE during previous functional tests. Snubbers found inoperable during functional testing shall be restored to OPERABLE status prior to resuming operation. For each snubber found inoperable during these functional tests, an additional minimum of 10% of all snubbers or 10 snubbers, whichever is less, shall'also be functionally tested until no more failures are found or all snubbers have been functionally tested. d. -Snubbers served by a common hydraulic reservoir are indicated by a bracket in Table 2.7-4. All reservoirs _ serving more than one snubber shall be inspected to ensure adequate hydraulic level : 1. Within 7 days after reactor startup"following a major outage or following any maintenance in the 'immediate vicinity of these snubbers, reservoirs or associated hydraulic piping; and l 2. Every 31 days + 25 percent. l I J l l l l L CALVERT CLIFFS-UNIT 1 3/4 7-26 Amendment No. 55 CALVERT CLIFFS-UNIT 2 Amendment No. JD,38

'J TABLE 3.7-4 i 's 'n'} SAFETY RELATED HYDRAULIC SNUBBERS * -i l' l. 'l SilllBBER SYSTEM SNUBBIR INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT i c'! 11 0. ON, LOCATION AND ELEVATION INACCESSIBLE ZONE ** TO REMOVE 5: (A or I) (Yes or No) (Yes or No) ~' - I-61-17 CONTAINMENT SPRAY D/STRM ~' S/0 ll/X -15' A No No I-61-9 S.G. #11 BLOWDOWN ORIFICE LINE 70' I Yes 'No I-63-10 S.G. #11 BLOWDOWN ORIFICE BYPASS 78' I Yes No l l-63-11 NITROGEN to S.G. #12 74' I Yes No 1-63-12 NITROGEN to S.G. #12 69' I Yes No i b~ 1-63-13 STEAM GENERATORS 75'- I .Yes No l E'l 1-63-14 STEAM GENERATORS 75' I Yes No I-63-15 STEAM GENERATORS 75' I Yes No 1-63-16 SIEAM GENERATORS 75' I Yes No 1-63-17 STEAM GENERATORS 75' I Yes No a8 i 0 ,P W k

T_ABLE 3.7-4 9 4 G -SAFETY RELATED HYDRAULIC SNUBBERS

• g

--i l P SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION-ESPECIALLY DIFFICULT M NO. ON, LOCATION AND ELEVATION INACCESSIBLE ZONE ** TO REMOVE y (A or I) (Yes or No) (Yes or.No) b 1-63-18 STEAM GENEPATORS 75' I Yes .No l 1-63-19 STEAM GENERATORS 75' I Yes-No ? ~ 1-63-20 STEAM GENERATORS 75'- I Yes No l-63-21 STEAM GENERATORS 75'- I Yes No l l l-63-22 STEAM GENERATORS 75' I .Yes No i 1-63-23 STEAM GENERATORS 75' I Yes No i y 1-63 24 STEAM GENERATORS 70' I Yes No- ? l-63-25 STEAM GENERATORS 75' I Yes No 10 5 1-63-26 STEAM GENERATORS 75' I Yes No i 1-63-27 STEAM GENERATORS 75' I Yes No f 1-63-28 STEAM GENERATORS 75'- I Yes No i } k 1-64-1 LINE TO PRESS. RELIEF A MOV-403 81' I Yes No 5 w i 1 s

c, -TABLE 4.7-4 ?:- si HYDRAULIC SNUBBER INSPECTION SCHEDULE ~~ Si c, [ ' NUMBER OF SNUBBERS FOUND INOPERABLE NEXT REQUIRED 41 DURING INSPECTION OR DURIN0L INSPECTION INTERVAL

• INSPECTION INTERVAL **

i v. $E il 0 18 months + 25% 1 12 months T 25%. 2 6 months T 25% 3 or 4 124 days T 25% 5, 6, or 7 62 days ][25% >8 31 days + 25% t i I 10 ? O i J

• Snubbers may be categorized into two groups,*" accessible" an( " inaccessible". This categorization shall i

El be based upon.the snubber's accessibility for inspection during reactor operation. These two groups may be i 2 inspected independently according to the above schedule. l 5 The required inspection interval shall not be lengthened more than one step at a time. ea 1 N i } 1 i e

REFUEtING OPERATIONS CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING LIMITING CONDITION FOR OPERATION 3.9.7 Loads in excess of 1600 pounds shall be prohibited from travel over fuel assemblies in the storage pool. APPLICABILITY: With fuel assemblies' in the storage pool. ACTION: With the requirements of the above specification not satisfied, place the crane load in a safe. condition. The provisions of Specification 3.0.3 are not applicable. SURVEILLANCE REQUIREMENTS 4.9.7 The weight of each load, other than a fuel assembly and CEA, shall be verified to be < 1600 pounds prior to Moving it over fuel assemblies. h J i CALVERT CLIFFS - UNIT 1 CALVERT CLIFFS UNIT 2 3/4 9-7

REFUELING OPERATIONS ~ SHUTDCWN COOLING AND COOLANT CIRCULATION LIMITING CONDITION FOR OPERATION ~ 3.9.8.1 At least one shutdown cooling loop shall be in operation.* APPLICABILITY: MODE 6 at all reactor wat'er levels. ACTION: a. With less than one shutdown cooling loop in operation, suspend l all operations involving an. increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System. Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours. The shutdown cooling pumps'may be de-energized during the time intervals required for local leak-rate testing of containment penetration number 41 pursuant to the requirements of Specification 4.6.1.2.d and/or to permit maintenance on valves located in the common shutdown cooling sucticn line, provioed (1) no operations are permitted which could cause dilution of. the reactor coolant system boron concentration, (2) all CORE ALTERATIONS are suspended (3) all containment penetrations'providing direct access from the containment atmosphere to the outside atmosphere are maintained closed, and (4) the water level above the top of the irradiated fuel is greater than 23 feet. b. The. provisions of Specification 3.0,3 are not applicable. SURVEILLANCE REQUTREMENTS 4.9.8.1 A shutdewn cooling loop'shall be determined.to be in operation and circulating reac;or coolant at a flow rate of > 3000 gpm** at least once per 4 hours. a

• The shutdown _ cooling loop may be removed from operation for up to 1 hour per 8 hour _ period during the parformance of CORE ALTERATIONS in the vicinity of l

l the reactor pressure vessel hot legs.

• • > 1500 gpm when the Reactor Coolant System is drained to a level below the midplane of the hot leg.

CALVERT CLIFFS - UNIT 1 Amendment No. 3$, 55 CALVERT CLIFFS - UNIT 2 3/4 9-8 Amendment No. 37, 38 l I

REFUELING OPERATIONS SHUTD0'WN'005LINGANDCOOLANTCIRCULATION LIMITING CONDITION FOR OPERATION 3.9.8.2 ' Two (2) independent shutdown cooling locos shall-be OPERABLE *#. APPLICABILITY: Mode 6 when the water level above the top of the irradiated fuel assemblies seated within the reactor pressure vessel is less than 23 feet. ACTION: a. With less than the required shutdown cooling loops OPERABLE, i~nitiate corrective action to return loops to OPERABLE status within one hour. b. The provisions of Specification 3.0.3 are not applicable. SURVEILLANCE REQUIREMENTS 4.9.8.2 No additional Surveillance Requirements other than those required by Specification 4.0.5. 4 I J

• Normal or emergency power source may be inoperable for each shutdown cooling loop.

1. 0ne shutdown. cooling loop may be replaced by one spent fuel pool cooling loop when it is lined up to provide cooling flow to the irradiated fuel in the reactor core and the heat generation rate of the core is below the heat' removal capacity of the spe.it fuel pool cooling loop.

CALVERT CLIFFS - UNIT 1 Amendment No. 55 CALVERT CLIFFS - UNIT 2 3/4 9-8a Amendment No. 38

3/4.15 SPEdIAL TEST EXCEPTIONS SHUTOOWN MARGIN' LIMITING CONDITION FOR OPERATION 3.10.1 The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 may be suspended for measurement of CEA worth and shutdown margin provided reactivity equivalent to at least the highest estimated CEA worth is available for trip insertion from OPERABLE CEA(s). APPLICABILITY: MODE 2. ACTION: a. With any full length CEA not. fully inserted and with less than the above reactivity equivalent available for t. f p insertion, immediately initiate and continue boration at > 40 gpm of 2300 l ppm boric' acid solution or its equivalent untiT the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored. b. With all full -length CEAs inserted and the reactor subcritical by less than the above reactivity equivalent, immediately initiate and continue boration at > 40 gpm of 2300 ppm boric l acid solution or its' equivalent until the SHUTDOWN MARGIN re-quired by Specification 3.1.1.1 is restored. SURVEILLANCE REQUIREMENTS 4.10.1.1 The position of each full length CEA required either partially or fully withdrawn shall be determined at least once per 2 hours. 4.10.1.2 'Each CEA not fully inserted shall be demonstrated capable of full insertion when tripped from at least the 50% withdrawn position with-in 24 hours prior to reducing the SHUTOOWN MARGIN to less than the limits t of Specification 3.1.1.1. i l CALVERT CLIFFS - UNIT 1 3/4 10-1 Amendment No. 37,48 CALY:itY CLIFFS - 0;:IT 2 Axndment ::o. 72. 31

SPECIAL TEST EXCEPTIONS MODERkTOR TEMPERATURE COEFFICIENT, CEA INSERTION AND POWER DISTRIBUTION LIMITS. LIMITING CONDITION FOR OPERATION 3.10.2 The moderator temperature coefficient, the CEA insertion and the power distribution limits of Specifications 3.1.1. 4, 3.1. 3.1, 3.1. 3. 5, 3.1. 3. 6, 3.2.2, 3.2.3, and 3.2.4 may be suspended during the performance of PHYSICS TESTS provided: a. The THERMAL-POWER is restricted to below 85% of RATED THERMAL POWER, and b. The limits of Specification 3.2.1 are maintained and determined as specified in Specification 4.10.2.2 below. APPLICABILITY: MODES 1 and 2. ACTION: With any of the limits of Specification 3.2.1 being exceeded while the require-ments of Specifications 3.1.1. 4, 3.1. 3.1, 3.1. 3. 5, 3.1. 3. 6, 3.2. 2, 3.2.3 and 3.2.4 are suspended, either: .a. Reduce THERMAL POWER sufficiently to satisfy the require-ments of Specification 3.2.1, or b. Be in H07 STANDBY within 6 hours. SURVEILLANCE REQUIREMENTS 4.10.2.1 The THERMAL POWER shall be determined at least once per hour during - CHYSICS TESTS in which the requirements of Specifications 3.1.1. 4. 3.1. 3.1, 3.1.3.5, 3.1.3.6. 3.2.2, 3.2.3 or 3.2.4 are suspended and shall be verified l to be within the test power plateau. 4.10.2.2 'The linear heat rate shall be determined to be within the limits of Specification 3.2.1 by monitoring it continuously with the Incore Detector Monitoring System pursuant to the requirements of Specifications 4.2.1.3 and 3.3.3.2 during PHYSICS TESTS above 5% of RATED THERMAL POWER in which the requirements of Specifications 3.1.1.4, 3.1.3.1 3.1.3.5, 3.1.3.6, 3.c.2, 3.2.3 or 3.2.4 are suspended. CALVERT CLIFFS - UNIT 1 Amendment No. 27, 55 CALVERT CLIFFS - UNIT 2 3/4 10-2 Amendment No. 38 N.

3/4-1 REACTIVITY CONTROL' SYSTEMS-BASES j 3/4.1.1 BORATION CONTROL [- 3/4.1.1.1 and 3/4.1.1.2 SHUTDOWN MARGIN ~ 4-l A sufficient SHUTOOWN MARGIN ensures that 1) the reactor can be made subcritical from all operating conditions, 2) the reactivity transients associated with postulated accident conditions are controllable within acceptable limits, and 3) the reactor will be maintained sufficiently subcritical to preclude inadvertent-criticality in the shutdown condition. SHUT 00WN MARGIN requirements vary throughout core life as a function of fuel depletion, RCS boron concentration and RCS T The minimum available SHUTDOWN MARGIN for no load operating conditions $E9beginning of life is 4.1% ak/k and at end of life is 4.3% ak/k. The SHUTDOWN MARGIN is based on the safety analyses performed for a steam line rupture event initiated at no load conditions. The most restrictive steam line rupture event occurs at E0C conditions. For the steam line. rupture event at beginning of cycle conditions, a minimum SHUTDOWN MARGIN of less than 4.1% ak/k is required to. control the reactivity transient, and end of cycle conditions require 4.3% ak/k. Accordingly, theSHUT00WNMARGINrequirementisbaseduponthislimitingconditjonandis consistent.with FSAR safety analysis assumptions. With T < 200 F, the reactivity transients resulting from any postulated accid 8d are minimal and a 3% ak/k shutdown margin provides adequate protection. With the pressurizer level less than 90 inches, the sources of non-borated water are restricted to increase the time to criticality during a boron dilution event. 3/4.1.1.3 BORON DILUTION. A minimum flow rate of at least 3000 GPM provides adequate mixing, prevents stratification and ensures that reactivity changes will be gradual during boron concentration reductions in the Reactor Coolant System. A flow rate of at least 3000 GPM will circulate an equivalent ' Reactor C;olant System volume of 9,601 cubic feet in approximately 24 minutes. The reactivity change rate associated with baron concen-tration reductions will therefore be within the capability of operator recognition and contrcl. 3/4.1.1.4 MODERATOR TEMPERATURE COEFFICIENT (MTC) The limitations on MTC are provided to ensure that the assumptions used in the accident and transient analyses remain valid through each fuel cycle. The surveillance requirements for measurement of the MTC jduringeachfuelcycleareadequatetoconfirmtheMTCvaluesincethis coefficient changes slowly due principally to the reduction in RCS boron concentration associated with fuel'burnup. The confirmation that the measured MTC value is within its limit provides assurances that the coefficient will be maintained within acceptable values throughout each fuel cycle. CALVERT CLIFFS - UNIT 1 B 3/4 1-1 Amendment No. 27, 22,4r, CALVEf!T CLIFFS - UNIT 2 Amendment No. 73, 31

REACTIVITY CONTROL SYSTEMS-BASES 13/4.1.1.5 MINIMUM TEMPERATURE FOR CRITICALITY This specification ensures that the reactor will not be made crijicalwiththeReactorCoolantSystemaveragetemperaturelessthan 515 F. This limitation is required to ensure 1) the moderator temperature coefficient is within its analyzed temperature range, 2) the pre.ective -instrumentation is within its normal operating range, 3) the pressurizer is capable of being-in an OPERABLE status with a steam bubble, and 4) the reactor pressure vessel is above its minimum RT tempenture. NOT 3/4.1. 2 BORATION SYSTEMS The. boron injection system ensures that negative reactivity control is available during each mode of facility operation. The components required to perform this function include 1) borated water sources, 2) charging pumps, 3) separate flow paths, 4) boric acid pumps, 5) associated heat tracing systems, and 6) an emergency power supply from OPERABLE diesel generators. 0 With the RCS average temperature above 200 F, a minimum of two separate and redundant'bcron injection systems are provided to ensure single functional capability in the event an assumed failure renders one of the systems inoperable. Allowable out-of-service periods ensure that minor component repair or corrective action may be completed without undue risk to overall facility safety from injection system failures during the repair period. The boration capability of either system is sufficient to provide a ~ SHUTOOWN MARGIN from all gperating conditions of 3.0% ak/k after xenon decay and cooldown to 200 F. The maximum boration capability requirement occurs at EOL from full power equilibrium xenon conditions and requires 6500 gallons of 7.25% boric acid solution from the boric acid tanks or 55,627, gallons of 2300 ppm borated water from the refueling water tank. However, to be consistent with the ECCS requirements, the RWT is required to have a minimum contained volume of 400,000 gallons during MODES 1, 2, 3 and 4. The maximum boron concentration of the refueling water tank shall be limited to 2700 ppm and the maximum boron concentra-tion of the boric acid storage tanks shall be limited to 8% to preclude the possibility of coron precipitation in the core during long term ECCS cooling. With the RCS temperature below 200 F, one injection system is acceptable without single failure consideration on the basis of the stable' reactivity condition of the reactor and the additional restric-tions prohibiting CORE ALTERATIONS and positive reactivity change in the event the single injection system becomes inoperable. CALVERT CLIFFS - UNIT 1 Amendment No. 27, 4, 55 CALVERT CLIFFS - UNIT 2 8 3/4 1-2 Amendment No. 31

3/4.2 POWER DISTRIBUTION LIMITS BASES 3/4.2.1 LINEAR HEAT RATE The limitation on linear heat rate ensures that in the event of a LOCA, the peak temperature of the fuel cladding will not exceed 2200*F. Either of the two core power distribution monitoring systems, the Excore Detector Monitoring System and the Incore Detector Monitoring System, provide adequate monitoring of the core power distribution ar.d are capable of verifying that the linear heat rate does not exceed its 1;mits. The Excore Detector Monitoring System performs this function by continu-ously monitoring the AXIAL SHAPE INDEX with the OPERABLE quadrant symmetric excore neutron flux detectors and verifying that the AXIAL SHAPE INDEX is maintained within the allowable limits of Figure 3.2-2. In conjunction with the use of the excore monitoring system and in establishing the AXIAL SHAPE INDEX limits, the following assumptions are made: 1) the CEA insertion limits of Specifications 3.1.3.5 and 3.1.3.6 are satisfied, 2) the flux peaking augmentation factors are as shown in Figure 4.2-1, 3} the AZIMUTHAL POWER TILT restrictions of Specification 3.2.4 are satisfied, and

4) the TOTAL PLANAR RADIAL PEAKING FACTOR does not exceed the limits of Specification 3.2.2.

The Incore Detector Monitoring System continuously provides a direct measure of the peaking factors and the alarms which have been established for the individual incore detector segments ensure that the peak linear heat rates will be maintained within the allowable limits of Figure 3.2-1. The setpoints for these alarms include allowances, set in the conservative directions, for 1) flux peaking augmentation factors as shown in Figure 4.2-1, 2) a measurement-calculational uncertainty factor of 1.070, 3) an l engineering uncertainty factor of 1.03, 4) an allowance of 1.01 for axial fuel densification and thennal expansion, and 5) a THERMAL POWER measurement uncertainty factor of 1.02. 1 3/4.2.2, 3/4.2.3 ard 3/4.2.4 TOTAL PLANAR AND INTEGRATED RADIAL PEAKING FACTORS - Fh AND Ff AND AZIMUTHAL POWER TILT - T y T The limitations on F and T are provided to ensure that the assump-tions used in the analysis # or esEablishing the Linear Heat Rate and Local f Power Density - High LCOs and LSSS setpoints remain valid during operation af the various allowable CEA group insertion limits. The limitations on r e and T are.provided to ensure that the assumptions used in r q

ALVERT CLIFFS - UNIT 1 B 3/4 2-1 Amendment No. 33, 39 l

lALVERT CLIFFS - L$1T 2 .ucadacnt :.o.' 78, 24 l l

POWER DISTRIBUTION LIMITS BASES the analysis establishing the DNB Margin LCO, and Thermal Margin / Low Pressure LSSS setpoints remain valid ~duringT per9 tion at the various allowable CEA group insertion limits. If F F or T exceed their basic limitations, operation may continue ufuler Ehe ad0itional restric-tions. imposed by the ACTION statements since these ~ additional restric-tions provide adequate provisions to assure that the assumptions used in establishing the Linear Heat Rate, Thermal Margin / Low Pressure and Local Power Density - High LCOs and LSSS'setpoints remain valid. An AZIMUTHAL POWER TILT > 0.10 is not expected and if it should occur, sub-sequent operation would be restricted to only those operations required to identify the_ cause of this unexpected tilt. T JhevalueofT that must be used in the equation F*Y = F*7 (1 + T ) 9 r (1+T ) is the measured -tilt. and F =F q r T The surveillance requirements for verify.ing that F F and T within their limits provide assurance that the actual v Yues 9fFTqFaye T r and T do not exceed the assumed values. Verifying F and F afNr each 9uel loading prior to exceeding 75". of RATED THENEIAL POWER provides additional assurance that the core was properly loaded. l 3/4.2.5 DNB PARAMETERS The limits on the ONB related parameters assure that each of the parameters are maintained within the nomal steady state envelope of l operation assumed in the transient and accident analyses. The limits are consistent with the safety analyses assumptions and have been analytically demonstrated adequate to maintain a minimum DNBR of 1.195 throughout each analyzed" transient. The 12 hour periodic surveillance of these parameters through instru-ment readout is sufficient to ensure that the parameters are restored l within their limits following load changes and other expected transient l operation. The 18 month periodic measurement of the RCS total flow rate l 1s adequate to detect flow degradation and ensure correlation of the i flow indication channels with measured flow such that the indicated l percent flow will provide sufficient verification of flow rate on a l 12 hour basis. CALVERT CLIFFS - UNIT 1 B 3/4 2-2 Amendment No. 33, /g, 55 CALVERT CLIFFS - UNIT 2 Amendment ?!o. 78, 37, 38 l

W 3/4.4 REACTOR COOLANT SYSTEM BdSES. w 3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION -The plant -is designed to operate,with both reactor coolant loops and - l associated reactor coolant pumps in. operation, and maintain DNBR above 1.195 l during all normal: operations and anticipated transients. I A single reactor coolant loop with it's' steam generator filled above the low level ~ trip setpoint provides sufficient heat removal capability'for core ~ cooling while in MODES 2 and 3; however. single failure considerations require plant shutdown if component repairs and/or corrective actions cannot be made within the allowable.out-of-service time. - 3, In MODES 4 and 5, a single reactor coolant loop or shutdosn _ cooling. loop i provides ' sufficient heat removal capatility for removing decay heat; but. single failure considerations require that at least two loops be.0PERABLE. Thus, if a ] the reactor coolant loops are.not OPERABLE.; this specification requires two_ shutdown. cooling loops to be OPERABLE. The operation of one Reactor Coolant Pump or one shutdown cooling pump provides adequate flow'to ensure mixing, prevent stratification and produce gradual reactivity changes during baron concentration reductions in the Reactor Coolant ~ System. The' reactivity change rate associated with boron reductions l will, therefore, be. within the capability of operator recognition and control. The restrictions on starting a Reactor Coolant Pump during MODES 4 and 5 i, with one or more RCS cold legs < 275 F_ are provided to prev *nt RCS pressure transients,' caused by energy adifitions.from the secondary system, which could exceed the limits of Appendix G to 10 CFR-Part 50. The' RCS will be protected against overpressure transients and will not exceed the limits of Appendix G by either.-(l) restricting the water volume in the pressurizer and thereby t' providing' a volume for.the primary coolant to expand into or (2) by restrict-ing starting of the.RCPs to wheg the gecondary water temperature ofceach steam generator.-is less than 46 F (34.F when meas' red by a surface contact u t l instrument) above the coolant: temperature in the reactor ves'sel. J 3/4.4.2 SAFETY VALVES The pressurizer code safety valves operate to prevent the RCS from being pressurized above igs Safety Limit of 2750 psia. Each safety valve is designed l to relieve 7.6 x 10 lbs per hour of saturated steam at the valve setpoint. The relief capacity _of a single safety valve is adequate to relieve any overpressure condition which could occur during shutdown. In the event that no safety valves i are OPERABLE, an operating shutdown cooling loop, connected to the RCS, provides overpressure: relief capability and will prevent RCS overpressurization. During operation.all~ pressurizer code safety valves must be OPERABLE to prevent the RCS from being pressurized above its safety limit of 2750 psia.- The combined relief capacity of these valves is sufficient to CALVERT CLIFFS . UNIT 1 Amendment No. M, 53,55 CALVERT CLIFFS . UNIT 2 B 3/4 4-1 Amendment No. 78, 36,38 1 .-. --..-.aa.-

REACTOR COOLANT SYSTEM BASES limit the Reactor Coolant System pressure to within its Safety Limit of 2750 psia following a complete loss of turbir.e generator load while operat-ing at MTED THERMAL POWER and assuming no reactor trip until the first Reactor Protective System trip setpoint.(Pressurizer Pressure-High) is reached (i.e., no credit is taken for a direct reactor trip on the loss of turbine) and also assuming no operation of the pressurizer power operated relief valve or. steam dump valves.. Demonstration of the safety valves' lift settings will occur only during shutdown and will be performed in accordance with the provisions of .Scction XI of the ASME Boiler and ?ressure Vessel Code. 3/4.4.3 RELIEF VALVES The power operated relief valves (PORVs) operate to relieve RCS pressure ~ below the setting of the pressurizer code safety valves. These relief valves have remotely operated block valves to provide a positive shutoff capability should a relief valve become inoperable. The electrical power for both the relief valves and the block valves is capable of being supplied from an emergency power source to ensure the ability to seal this possible RCS leak-age path. 3/4.4.4 PRESSURIZER A steam bubble in the pressurizer with the level as programmed ensures that the RCS is not a hydraulically solid system and is capable o. 'ccommo-dating pressure surges during operation. The' programmed level alsu protects the pressurizer code safety valves and power operated relief valve against water relief. The power operated relief valves function to relieve RCS pressure during all design transients. Operation of the power operated relief valve in conjunction with a reactor trip on a Pressurizer--Pressure-High signal, minimizes the undesirable opening of the spring-loaded pressurizer code safety valves. The requirement.that 150 kw of pressurizer heaters and their associated l controls be capable of being supplied electrical power from an emergency bus provides assurance that these heaters can be energized during a loss of off-site power condition to maintain natural circulation at HOT STANDBY. 3/4.4.5 STEAM GENERATORS. The Surveillance Requirements for inspection of the steam generato, tubes ensure that the structural integrity of this portion of the RCS will be maintained. The program for inservice inspection of steam generator tubes is based on a modification of Regulatory Guide 1.83, Revision 1. Inservice inspection of steam generator tubing is essential in order to CALVERT CLIFFS - UNIT 1 B 3/4 4-2 Amendment No. M, 53 CALVERT CLIFFS - UNIT 2 Amendment No. M, 36

3/4.9 REFUELING OPERATIONS i BASES l 3/4.9.1 BORON CONCENTRATION The limitations on minimum boron concentrattu.. (2300 ppm) ensure that: l

1) the reactor.will remain subcritical during CORE ALTERATIONS, and 2) a uniform boron concentration is maintained for reactivity control in the water volumes having direct access to the reactor vessel. The limitation on K

of no greater than 0.95 which includes a conservative allowance for ubrtainties, is sufficient to prevent reactor criticality during refueling operations. 3/4.9.2 INSTRUMENTATION, -The OPERABILITY of the source range neutron flux monitors ensures that redundant monitoring capability is available to detect changes in the reactivity. condition of the ccre. 3/4.9.3 DECAY TIME The minimum requirement for reactor subcriticality prior to movement of irradiated fuel assemblies in the reactor pressure vessel ensures that sufficient time has elapsed to allow the radioactive decay of the short lived fission products. This decay time is contristent with sie assumptions used in the accident analyses. 3/4.9.4 CONTAINMENT PENETRATIONS The requirements on containment peatration closure and OPERABILITY ensure that a release of radioactive material within containment will be ~ restricted from leakage to the environment. The OPERABILITY and closure i restricti*ons are sufficient to restrict radioactive material release I from a fuel element rupture based upon the lack of containment pressur-ization potential while in the REFUELING MODE. 3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling l L station personnel can be promptly informed of significant changes in the facility status or core reactivity condition during CORE ALTERATIONS. CALVERT CLIFFS - UNIT 1 B 3/4 9-1 Amendment No. 48 l CALVERT CLIFFS - U::IT 2 Auendaant No. 31 i .-. ~

REFUELING OPERATIONS BASES' 3/4.9.6 REFUELING MACHINE OPERABILITY The OPERABILITY requirements for the refueling machine ensure that: (1) the refueling machine will be used for movement of CEAs and fuel assemblies, (2) the refueling machine has sufficient load capacity to lift a CEA nr fuel assembly,. and (3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations. 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING The restriction on movement of loads in excess of t.e m.*m.' weight of a fuel assembly'and CEA over other fuel assemblies in the storage pool ensures that in the event this load is dropped (1) the activity release will be limited to that contained in a single fuel assembly, and (2) any possible * 'tortion of fuel in the storage racks will not result in a critical array. Tn!s assumption is consistent with the activity release assumed in the accident analyses. 3/4.9.8 COOLANT CIRCULATION The requirement that at least one shutdown cooling loop be in operation ensures that (1) sufficient cooling capacity is available to repve decay heat and maintain the water in the reactor pressure vessel below 140 F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification. The requirement to have two shutdown cooling loops OPERABLE when there is less than 23 feet of water above the core ensures that a single failure of the operating shutdown cooling loop will not result in a complete loss of decay heat removal capability. With the reactor vessel head removed and 23 feet of water above the core, a large heat sink is available for core cooling, thus in the event of a failure of the operating ~ shutdown cooling loop, adequate time is provided to initiate emergency procedures to cool the core. l 3/4.9.9 CONTAINMENT PURGE VALVE ISOLATION SYSTEM The OPERABILITY of this system ensures that the containment purge valves will be automatically isolated upon detection of high radiation levels within the containment. The OPERABILITY of this system is required to restrict the L release of radioactive material from the containment atmosphere to the environment. l CALVERT CLIFFS - UNIT 1 Amendment No. 55 l CALVERT CLIFFS - UNIT 2 B 3/4 9-2 Amendment No. 33 l

O O 4 5 4 me c.= Y u.,.J --. _ J 1..a i. A. - i- ~~.. = -,- ~ h .,s. .2-.- 2. w.-~. =

• c.wtove es% a scrt 4

t b f!? 5 9 + a + C -...s.( ll-.. w g.a N. - Py : ,,..f : s!.*..-.,- .~ -=~ d -~'

**' sf f tg

. [... , -. %.1.p - w .e 2

• f*-

g ca;fr . 4 v,s e ,_ ' jf+ %.. a ~ s 3 .s ?. R_y . -j e ,.g ~ <. _p., e :.. g., '., ~e -_y' s. l f mfC-i p }. p e ^J:\\ e. './. . ;E.* ~ .c. .?" '. ) 4., a. ~ s { / . s..p,4

g s

w 4 w 4 v.

r,mw

.. g- -.- s ..r...- g g ' f.,,.-. .rm y y .?- / . *.,...-... 4 s v -.. - s. ]..a u en ,.4 p s )/^/ * ) \\ T.Ti l' ] % f, *,_-_,

f. ' $,Q.

1 ,' ;~ .._ ; ? y_-- b g 1., y M, =.n, s

D

-c. a - s

, c F. 6, s ;,

o,,8... Wg. a.0 .p,>' 1' ' ],'. ^* ~ [ ' r i,- t N-s. ,<.{, .: - ?. < ks>&, -1% ' f'.,J_.. _ ..4 'E'.: 47 f)..,t,f 3.W;,q . k W . L,% ~ c '. L-t 's..,4 'h J;% ?s'p. \\ w= p g',. 5.,,, b- .__f C i.. ,) .g S'- * $ ff ) ....:9.:p[,g.njv.D.y 4 :$ 4,...c s. g.,' s. s,: s- -:-c. { n $'.\\.* ... A,g. 3,,:,,, Q 3 9);:, M_4 r,.P --w % .g. y. ..c Q

yg~/ h.,.f....)$f.^.*h. _h

V r,_ p,, 9..,f1.:*a;$ f , 3 M.f."l; L.ff .o . r.. :..y.., . ; bp % c, g ,sef: - c 4,9 a :.. ~ &y h' $ 's.i. ' &b:.flji 4 n b: f n k-flDi,h 2.d..f5 ?f'b [: J.;r.'D$MQ ',1G ':p.k,2 LOW POPULATION ZONE F I G. 5.1 - 2 CALVERT CLIFFS - UNIT 1 CALVERT CLIFFS - UNIT 2 5-3 ~

DESIGN FEATURES DESIGN PRESSURE AND TEMPERATURE 7 5.2.2 The reactor containment building is designed and shall,be main-tained for a maximum internal pressure of 50 psig and a temperature of 276*F. 5.37-REACTOR CORE' FUEL ASSEMBLIES 5.3.1 ~ The reactor core-shall contain 217 fuel assemblies with each fuel. assembly containing a maximum of 176 fuel rods clad with Zircaloy-4. Each fuel rod shall have a nominal active. fuel length of 136.7 inches and contain a maximum total weight of 3000 grams uranium. The initial core loading shall have a. maximum enrichment of 2.99 weight percent U-235. Reload fuel shall be stmilar in physical design to the. initial core loading and shall have a maximum enrichment of 3.7 weight percent U-235. 5.3.2 Except-for special-test as authorized by.the NRC, all fuel assemblies under control element assemblies shall be sleeved with a sleeve design previously approved by the NRC. CONTROL ELEMENT ASSEMBLIES i 5.3.3 The reactor core shall-contain 77 full length and no part length t control element assemblies. 5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained: i' a. In accordance with'the code requirements specified in Section 4.2 of the FSAR with allowance for normal degradation pursuant c i. of the applicable Surveillance Requirements, b. For a pressure of 2500 psia, and c. For a tenperature of 650*F,'except for the pressurizer which is 700*F. ~ 1 4 4 inLVERT CLIFFS - UNIT 1 Amendment No. 32, 55 g CALVERT CLIFFS - UNIT 2 5 -4 Amendment No. 18,31 . ~, - - - -. -.. -... - - -.. -.

UNITED STATES E NULLEAR REGULATORY COMMISSION

,I WASMNGTON, D. C. 20555

/ BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. S0-318 CALVERT CLIFFS NUCLEAR ~ POWER PLANT UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 38 License No. DPR-69 1. The Nuclear Regulatory Commission (the Ccmmission) has found that: A. The application for amendment by Baltimore Gas & Electric Company (the licensee) dated January 8,1981, and corrective information provided by letters dated February 5, March 24 and April 9,1981, 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 conforaity 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 thd public, and (11) 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. l'he issuance of this amendment is in accordance with 10 CR 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. OPR 69 is hereby amended to read as follows: 2. Technical Specifications The Technical Specifications cont ined in Appendices A and G, as revised through Amendment No. 38, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications. h' _m,

2- + 3. This license amendment is effective on July 1,1981, FbR TiiE fiUCLEAR REGULATORY COR'ilSSION '( y k ' ki W' ~ RdbertA. Clark,-Chief Operating Reactors Branch f3 Division of-Licensing -

Attachment:

Changes to:the, Technical Specifications Date of Issuance: June 16, 1981~ G e e e e h } 1 e es e 9"- g -W Y-F'4-2 mMg y y-q,wsy_- y.._,_,%,g ,3,,

• ATTACHMENT TO LICENSE AMENDMENT N05. 55 AND 38 FACILITY OPERATING LICENSE NOS. OPR-53 AND DPR-69 DOCKET NOS. 50-317 AND 50-318 Replace the following pages of the Appendix A Technical Specifications for

.both units with the' enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the e area of change. The corresponding overleaf pages are also provided to maintain document completeness. Pages Pages IV' 3/4 4-2a (new page) ~ VIII (separate pages) 3/4 4-2b (new page) IX. 3/4 5-1 X 3/4 5-2 XIII 3/4 5-7 2-12. (for clarity) 3/4 7-26 2-13 3/4 7-45 (Unit 2 only) 2-14 (remove) 3/4 7-46 (Unit 2 only) 2-15 3/4 7-51 (Unit 1 only) 2-16 3/4 7-52 (Unit 1 only) 2-17 3/4 7-53 (Unit 2 only) 2-18 3/4 7-62 (Unit 1 only) 2-19 3/4 9-8 3/4 1-3. 3/4 9-8a (new page) 3/4 1-16 3/4 10-2 3/4 1-23 8 3/4 1-2 3/4 2-8 (printing error) B 3/4 2-2 3/4 2-13 8 3/4 4-1 3/4 4-1 B 3/4 9-2 3/4 4-2 5-4 2 ..-,.,4-, 4-e -w--- ...-,---,c.~ .ow y--..

INDEX-LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.0 APPLICABILITY........................................... 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL- > 200*F....................... 3/4 1-1 ' Shutdown Margin - Tayg ,. Shutdown Margin - T i 200*F....................... 3/4 1-3 avg B o ro n D i l u t i o n...................................... 3/4 1-4 Moderator Temperature Coef ficient............... 3/4 1-5 Minimum Temperature for Criticality.................. 3/4 1-7 3/4.1.2 B0 RATION SYSTEMS . Flow Paths - Shutdown................................ 3/4 1-8 Flow Paths - Operating............................... 3/4 1-9 Charging Pump - Shutdown............................. 3/4 1-10 Charging Pumps - Operating........................... 3/4 1-11 Boric Acid Pumps - Shutdown.......................... 3/4 1-12 Boric Acid Pumps - Operating......................... 3/4 1-13 * - Borated Water Sources - Shutdown..................... 3/4 1-14 Borated Water Sources - Operating.................... 3/4 1-16 3/4.1.3 -MOVABLE CONTROL ASSEl% LIES ' 'Full Length CEA Position............................. 3/4 1-17 Pos ition Indicator Channel s.......................... 3/4 1 -21 CEA Drop Time........................................ 3/4 1-23 Shutdown CEA Insertion Limits........................ 3/4 1-24 Regulating CEA Insertion Limits...................... 3/4 1-25 CALVERT CLIFFS - UNIT 1 III Amendment No. 32 Amendment No. 18 CALVERT CLIFFS - UNIT 2 w-e-cekw +8 1----e-ew-i$ g- --,6, -v -+3 ,t.,+.+--t w w* ge y$ + p- ,*m e t-g wr g* wa w e-eve-, y w-Swa----n*7 gwet+-- 7 t--'*-T Y'-- v? t-m%

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 L I N EAR H EAT RAT E........................................ 3/4 2-1 3/4.2.2 TOTAL PLANAR RADIAL PEAKING FACTOR...................... 3/4 2-6 3/4.2.3 TOTAL INTEGRATED RADIAL PEAKING FACTOR.................. 3/4 2-9 3/4.2.4 AZIMUTHAL POWER TILT.................................... 3/4 2-12 3/4.2.5 DN B PA RAMETERS.......................................... 3/4 2-13 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION...................... 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM I NSTRUMENTATION....................................... 3/4 3-10 3/4.3.3' MONITORING INSTRUMENTATION Radiation Moni tori ng Instrumenta tion.................... 3/4 3-25 Incore Detectors........................................ 3/4 3-29 Sei smic Instrumentation................................. 3/4 3-31 Meteorological Instrumentation........'.'................. 3/4 3-34 Remote Shutdown Instrumentation......................... 3/4 3-37 Post-Accident Instrumentation........................... 3/4 3-40 Fire Detection Instrumentation.......................... 3/4 3-43 3/4.4 REACTOR COOLANT SYSTEM 3/4:4.1 dOOLANT LOOPS AND COOLANT CIRCULATION................... 3/4 4-1 S ta rtu p a nd Powe r....................................... 3/ 4 4-1 Ho t S t a n d by............................................. 3 / 4 4 - 2 Shutdown................................................ 3/4 4-2a 3/4.4.2 SAFETY VALVES........................................... 3/4 4-3 3/4.4.3 RELIEF VALVES........................................... 3/4 4-4 CALVERT CLIFFS - UNIT 1 IV Amendment No. 39, $3, 55 CALVERT CLIFFS - UNIT 2 Amendment No. 73, 36, 38 i

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION...... 3/4 7-13 3/4.7.3 COMPONENT COOLING WATER SYSTEM....................... 3/4 7-14 3/4.7.4 SERVICE WATER SYSTEM................................. 3/4 7-15 3/4.7.5 SALT WATER SYSTEM.................................... 3/4 7-16 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM........... 3/4 7-17. 3/4.7.7 ECCS PUMP ROOM EXHAUST AIR FILTRATION SYSTEM......... 3/4 7-21 3/4.7.8 HYDRAULIC SNUBBERS................................... 3/4 7-25 3/4.7.9 SEALED SOURCE C0NTAINMINATION........................ 3/4 7-55 3/4.7.10 WATERTIGHT D00RS..................................... 3/4 7-57 3/4.7.11 FIRE SUPPRESSION SYSTEMS Fire Suppression Water System........................ 3/4 7-58 Spray and/or Sprinkl er Systems....................... 3/4 7-62 Halon System......................................... 3/4 7-64 Fire Hose Stations................................... 3/4 7-65 3/4 7.12 PENETRATION FIRE BARRIERS.............:.............. 3/4 7-67 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES 0persting............................................. 3/4 8-1 Shutdown.............................................. 3/4 8-5 3/4'.8.2 6NSITEPOWERDISTRIBUTIONSYSTEMS A.C. Distribution 0perating......................... 3, 8-6 A.C. Distribution - Shutdown.......................... 3/4 8-7 0.C. Distri'autior. - Operating......................... 3/4 8-8 0.C. Distribution - Shutdown.......................... 3/4 8-11 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION.................................. 3/4 9-1 3/4.9.2 INSTRUMENTATION...................................... 3/4 9-? 3/4.9.3. DECAY TIME........................................... 3/4 9-3 -CALVERT CLIFFS-UNIT 2 VII Amendment No. 6, 11

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION' _PAGE 3/4.9.4 CONTAINMENT PENETRATIONS............................. 3/4 9-4 3/4.9.5 COMMUNICATIONS....................................... 3/4 9-5 3/4.9.6. REFUELING MACHINE OPERABILITY........................ 3/4 9-6 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING...... 3/4 9-7 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION............ 3/49 3/4.9.9 CONTAINMENT PURGE VALVE ISOLATION SYSTEM............. 3/4 9-9 3/4.9.10 WATER LEVEL - REACTOR VESSEL'......................... 3/4 9-10 3/4.9.11 SPENT FUEL POOL WATER LEVEL.......................... 3/4 9-11 3/4.9.12. SPENT FUEL P0OL VENTILATION SYSTEM................... 3/4 9-12 3/4.9.13 SPENT FUEL CASK HANDLING CRANE....................... 3/4 9-15 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN...................................... 3/4 10-1 3/4.10.2 MODERATOR TEMPERATURE COEFFICIENT, CEA INSERTION AND POWER DISTRIBUTION LIMITS......".~.............. 3/4 10-2 3/4.10.3 N0 FLOW TESTS........................ 3/4 10-3 3/4.10.4 CENTER CEA MISALIGNMENT.............................. 3/4 10-4 3/4.10.5 COOLANT CIRCULATION.................................. 3/4 10-5 A 4 CALVERT CL:FFS :.N 7 2 VI:I Are". rent'd.6.)).35

INDEX 11 BASES- ~l SECTION PAGE 3/4.0 APPLICABILITY.............................................. B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 80 RATION CONTROL......................................... B 3/4 1-1 3/4.1.2 B0 RATION SYSTEMS......................................... B 3/4 1-2 3/4.1.3 MOVABLE CONTROL ASSEMBLIES............................... B 3/4 1-3 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 LINEAR HEAT RATE......................................... B 3/4 2-1 3/4.2.2, 3/4.2.3. and 3/4.2.4 TOTAL PLANAR AND INTEGRATED T T AND AZIfiUTHAL q..........i?.ANDF RADIAL PEAKING FACTORS - F {.....................B3/42-1 POWER TILT - T 3/4.2.5 DNB PARAMETERS........................,................... B 3/4 2-2 3/4.3 INSTRUMENTATION 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURES INSTRUMENTATION............................... B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION................................ B 3/4 3-1 2 { CALVERT CLIFFS - UNIT 1 IX Amendment No. 27, 55 CALVERT CLIFFS - UNIT 2 Amendment No. 9, 38 P 'e4 " r *

• F f-E-w-

v' w'c? e et-4 =

• W wT^-+

tvV

• • T-"f
• "--'r "T

INDEX BASES SECTION PAGE 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION............... B 3/4 4-1 3/4.4.2 SAFETY VALVES........................................ B 3/4 4-1 3/4.4.3 RELIEF VALVES....................................... B 3/4 4-2 3/4.4.4 PRESSURIZER......................................... B 3/4 4-2 3/4.4.5 STEAM' GENERATORS.................................... B 3/4 4-2 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE...................... B 3/4 4-3 3/4.4.7 CHEMISTRY........................................... B 3/4 4-4 3/4.4.8 SPECIFIC ACTIVITY................................... B 3/4 4-4 3/4.4.9 PRESSURE / TEMPERATURE LIMITS......................... B 3/4 4-5 3/4.4.10 STRUCTURAL INTEGRITY............. B 3/4 4-12 3/4.4.11 CORE BARREL-MOVEMENT................................ B 3/4 4-12 3/4.4.12 LETDOWN LINE EXCESS FLOW............................ B 3/4 4-12 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 SAFETY INJECTION TANKS.............................. B 3/4 5-1 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS........................ B 3/4 5-1 3/4.5.4 REFU EL I NG WATER TAN K ( RWT ).......................... B 3/4 5-2 CALVERT CLIFFS - UNIT 1 Amendment No. 57,55 CALVERT CLIFFS - UNIT 2 X Amendment No. 6, 3W 38

INDEX BASES SECTION PA'GE 3/4.9.5 COMMUNICATIONS........................................ B 3/4 9-1 3/4.9.6 REFUELING MACHINE OPERABILITY......................... B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING............ B 3/4 9-2 3/4.9.8 ' SHUTDOWN COOLING AND COOLANT CIRCULATION............. B 3/4 9-2 3/4.9.9 CONTAINMENT PURGE VALVE ISOLATION SYSTEM............. B 3/4 9-2 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL AND SPENT FUEL POOL WATER LEVEL........................ B 3/4 9-3 3/4.9.12 SPENT FUEL'P00L VENTILATION SYSTEM................... B 3/4 9-3 3/4.9.13 SPENT FUEL CASK HANDLING CRANE....................... B 3/4 9-3 s 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN..................................... B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS............................................. B 3/4 10-1 3/4.10.3 NO FLOW TESTS........................................ B 3/4 10-1 3/4.10.4 CENTER CEA MISALIGNMENT.............................. B 3/4 10-1 3/(.10.5 ' COOLANT CIRCULATION................................. B 3/4 10-1 CALVERT CLIFFS - UNIT 1 Amendment No. 26, 55 CALVERT CLIFFS - UNIT 2 XIII Amendment No. 6, 77, 38

INDEX DESIGN FEATURES SECTION PAGE 5.1 SITE. -Exclusion Area............................................ 5-1 Low Po pul a ti o n Zo ne....................................... 5-1 5.2 CONTAINMENT Co n fi g u ra ti on............................................. 5-1 Design Pressure and Temperature........................... 5-4 5.3 REACTOR CORE Fuel Assemblies........................................... 5-4 Con trol El emen t As s embl ies................................ 5-4 5.4 REACTOR COOLANT SYSTEM Design Pressure and Tempera ture............ /.'............. 5-4 Vo1ume.................................................... 5-5 5.5 METEOROLOGICAL TOWER LOCATION............................. 5-5 5.6 FUEL STORAGE C r i t i c a l i ty............................................... .5-5 Drainage.................................................. 5-5 Capacity.................................................. 5-5 i 5.7 COMP 0NENT CYCLIC OR TRANSIENT L IMITS...................... 5-5 e CALVERT' CLIFFS - UNIT 1 XIV CALVERT CLIFFS - UNIT 2

1.30 UNACCEPTA BLE (0,1.25) UNACCEPTA BLE-2 OPERATION OPERATION sa .-e REGION /4 REGION EE l -\\ =

1. 2 0 - - - --, ---

j \\_ 4 l_. .-\\ -- -\\ __ _ :. : _. m i p___ _y j, _ -s- _. - w 1.1 _ ._=_ e. _0 -s,----+----------+------------_ o .i c. .l \\-D(+.2,1.00)'-'~~~----- a + _l 3 .00 __- - 1 -(. 2, 1. 00) =r y m E - __ j; ,g

g e

-\\ _ - -..\\;.. ,./ \\~4- '--- -.=_.: = _:. <C g 0.90 m rf x / \\ g

=

O m W g 0.80. -_._i____ /." \\-k --.. -,.T93~: U E -- -- _._ i s - = = = (-0.4[b775)i'/ Oggg0N --- 'y;(0.4,.75i ACCEPTABLE t- = = - - m ~ ~ u

0. 7.0 0.60

-0.6 -0.4 -0.2 0 0.2 0.4

0. 6 PERIPHERAL AXIAL SHAPE INDEX, Y1 j{I Figure 2.2-1 PERIPHERAL AXIAL SHAPE INDEX, Y VS FRACTION g

0F RATED THERt1AL POWER CALVERT CLIFFS - UNIT 1 Amendment No. 27, 2,4,48 LALVtHT CLIFFS - Uf.IT 2 2-11 Amendment tio. ),31

- nn r r-1 MM 1.5 --t --I !d h.I 1:. ' I J.!- i t i- '

t

.i.:::e : ;" 5 i. t rtr w-r r I +

i:, :

7>

--r

--Tg nn .6; c:t . in .e s 4r

. 4..

r ? 4 r r- --? ~ e-. m .- A g =-0.5 ASl + 1.10 - l: I i I- '~'..

t..

[ lp.. t-. - a n1 {.'. ; '"W1 "r1 41'. ...g-. M d .j ~y ~ -.I.- j,. {, [ ?.. '@.....

.g

l: b

}

. :R: a yj g4 g. i. y,4 g p l l bl'.-

. I'..

..j - - Q.. l ...4 y. I O

34

' $. J .s. t 5g L.7 EC '-. L....f. l 24 4

7

.4 ,l N l . a_ j

• j*j li 4 --

- t' -~ ' - --I 3-'"' r T' ..a m 9.... -- 9 = j. - - A-- "I 'pg,,,, j,3 4 mI'1. A g*+0.6 ASt +0.90'..,.j ;. 4 .l q..

1..

~ t i

4..:

i ]:

8

.k. ' g.-., 4 y-y, i ;y,,, e 4 ,:t.. 4 5-. . :a ir- , iy ..i.. i

o..4..

.. n. j s (4.2,1.20) 'I ..i ' ]. , i. l '._..l-21-t--- -- t - - -t-Ai 1.2 +' -. ~ j. ..i.j:.a ..j.... i.i. [: .5j ; . 0 .j.. .1 j.n. ...j..! p.a. .:.n z

2

) .t. v.

t..; -

.a. i. .s -:E.E 1 v \\t--:l9 --b -I-

---

}-:- -M-

. j (0.4,1.500) :. 3 ..V. i l :M - nkr-4 4-

i-

A:

m -- I 1 t 4:- ru r :- ik .t a b y'j % 'C.. E. g'.' ! 8l .l. h....g.. .a. i... ....n ....... l ..l 2 }..... . a.a ,9 n,,,,, .i i i g-g .r .. j.. ..t.. t 1

.tm

- O nOH i

F C;;H

--{~4~ DNB = Ay y j H 8 8 - 1 1.0 - + - - --r. ,PTRIP=2061(A )(OR )*1La5mT g3 9 VAR g g IN.8916 i l H +0.2,1.0001 - g i .)- l.... , }' _ i 9 L .L

t.. '

m I 8 m r } l } 8 i i

n. a i

g j. 1.' B g 1 i i l l l l l l e l l

• m 0.9 3

s -0.5 -0.4 4.3 0.2 0.1 0 0.1 0.2. o.3 0.4 0.5 Q to D ASI o o kL D I 7 FIGURE 2.2 2 g Thermal Margin / Low Pressure Trip Setpoint 1 Part 1 (ASI Versus A ) g D r-G 1

1.2 '.; ;.W =)l[... ii.H

. c

.th !;p:. = 1 l !' =a!![: tid .:!l :h j:il!H i j! j fi uf: tal ii !!F i a!h-.J n. .in.' i .n.na pi} !!"1 1.h .. E"p: t. n;p i t a,

pn.p.pr HLi pp an sq,, :y! n!:. @a nn n

.r t n to i; ;th :. t

p-a; j p: n. [.je h H" e

n f... i.r:h. .i

n n:

r o a .u nn n n-u m ..h. ^.:. 1j p. t L.:y...,l...}p: a.p; ap, :l: . h..-. h. h. jp. nn ni,

. h.

. E..:

a, l h,

?. c Iph

.p:

u:!..,j y e ni.! n.: h .:. JE. i. :. .~ ... r : = ..; u.c.

i;

a;j

...a L. p t r m: a.: un ..i v:

n un.

p u h. p. j r. h.ol: op i.1-

b n

n ; :..; :. 4 p ,n. o c-u

.:n :n:

n: n" nr

n u

in - n. n o 1.0 i;j:! p.;.

.h,.972'

[ ::F !,p

l' lU n

...:n.ihj li pt: =i.: =:l t i.yj nh f::. =.. '..== 1.j p: n ..i., .p =au.

u. x

..:. uu ut..= x.= m / :..l....- .l l,.. nt: ': up: 1;i

p

t r;

n;j l.- h-r p: M; i-

l Mi 1%

.".972 '.:j o:h; :j;; n{t " j ; ;- !"b:

n.

m e n- .l! h :- :!.n " t. ::: /

..-l

:n a:

p: to l a j:: :. i b- - u.. i j p- "il"il9" a

n! he

!' j ; !n. r.

n l

ft u:: :D r- .....n:

t:.

H: ^ 8G3 7

• n*r- =

T -"-~1]: -gr

i

.:n .h .,I: +;r " !~rm q.- ~}; = m Pt:

t. :. ! h..;

. : t :. i:; .:11 1t' o ./

t' N rll

....a. .t

"I t :. I. ;

M. I t n... -

t. !:

.t f., .t. ..t .t., .781lll;. ..r . 'a 0.8

1. 7,;/.... !. h.

!.:I.

n. l.

j...

i..,

... f. i:u... n!

.. n. ...[ . ! h.. @.. n...n. ; h..... n..

u.,,,j p

. ur

p

. p. ; . n.. - Hi n j; il;' ;iK jlll

p

p y

iJ ih

lll 'H

l; jijj !!! iiji llll R.

. >. f. ; c:

l:

h ,m i. u o

h: c. n nj-r

.h n. o

n

~ . /:~" 'i: : ,:n '___!/ 1 0.6 .. " ". l :.... 'El OR % '!ii df i. nI. 4 ' :t . /"- am c.. .n e. .p

r. :

.:p

r...- :,-

..n,;: i - r: i .2 n!:t .j iN!{!! ':i.!: II 0.4 m

!./..

n..

=b=r[r.t== =-: =}n: .a:- +

a;

.n r : ..am:. r= r- -t : n = .. }n

n. -.: nru =

t n -- =

.:n i c-,. :::- net::*-

in

= ":O NB*A xOR1 D 1 w .in C-.235:nh== :- = la and"=r::. utn 3- = i.

t::r e:

1- ... d=......=. l, e.... 0.2 q.. =. - -- pTRIP =2061xODN B +15.25 xTIN-8915 :. - ~j- "f"- ' UU ....f n. _.- .n r =.

n. _r..

yAR E5.E ~.r =Di 95 i=.Ei-:dMEi.if. Eif!55 Mlh. ik-I.~5 Nti!!

==;nr= t:= '-_ ;::..:atn . n-}u.. cube = n h -* tu f== ~~- --t= = ..at : -.:n .:n ::.. .. :t =

-t:a

t..=

l =.. " =t.:u--ln:*:-t--f:~J-i t.

n2=

0 ~ * - ~ = = pu : n...:g 0.. g . _ _ :n-t -enjr :. u = = 0 0.2 0.4 0.6 0.8 1.0 1.2 i FRACTION OF RATED THERMAL POWER l l l FIGURE 2.2 3 Thermal Margin / Low Pressure Trip Setpoint Part 2 (Fraction of RATED THERMAL POWER versus OR ) 3 i l CALVERT CLIFFS - UNIT 1 2-13 Amendment No. 27, 2#,39 CALVERT CLIFFS - UNIT 2 Amendment No. 9, J8 ~ P00R WW

~ 17d

= l = x.

= =_ : = u : : n :-

==

.f

I.--

F n

E. d..E_ [.=. i...

i.E_.E.. _~..

=-E. :E si.E.. .1. - = E 130

M:-i=@=5.-iMM=iP?i# " !# + :j-f si" 55 4'"

E - E 150 - f.= ___~_~ p=_ _ :- 1. := = =.:-. ... t .....s.=..__:. :. ._.l..._..._-.... p=.- - - + - - = = t..

==E fr. __ _f:. _- = -l -. _

n :i :: 2.15. 2.:..._=.L D....r=..

=uy:_E =_ ZEE:254 = E.... Ir. 120 -9..E=.l:- + -.,...... _.- t = E: ' =li: ~ as:=- =- t

===- ich. -E -~ ""I.~==T:EE-2il:':".-. E-5r'3" M. - h "' :"-@M 5 fE5'{"i ':M E S .__\\ : 3.Eg.E.=__. i_=_ = _== t..u nr=_..__:_; =. t.n-us __ _ T t..__.. cr..: -== i:2

. :rf.i_i.' _d_.E....

a z

t.

._:--,= = -

g.-.= y = =. = = t:=... :=- ::r - + - t u - ". t_ -- --- = nr -:r = - - - ---+- =t = - :- M W 2 - ;= . _._. _. :F=-- = =f.. ;:- =.l a r : 4. =.- =_ :. : _-.

==__:.=_ u rn.-

I.. :

e = nr : .. _ _;t==

-- r

__-t E .-4..

=--:__ - - - - -

-,_=--._

.---.g_;.. .-r--. zz.: = - --= ; =:z_;:g=r 3 _...._ - w 4 .J _a__.__. = t. : r

1..

_A.

~.

) w 110 2_ __ g,_. _. g=.._2_....u. .2._- __u-- 4 .=

-.:_ _ " - - =:=1

.=_.._ _.__...u=, g 3 2._.,__ g_. _..% _7_. __.3._.._,._.,.m w g _.-2.:_._= _ 2 _. _2-r...:- a. . _ _Qr., _-100 2 y . = _ = - -_ _ _...__.=.:... =

;,_.

_ _;g_=_.

=.

.g._ 4 >= p. 3-MOD ES 1, 2, 3, & 4 - ' ~p=~ - r~___ ...1- - ~ ~ - ' ~ ~ - ' - ~ 90 _ ~ y

_:-.- -/n 9 :=r la H :- i.

- t -- t - - e t --- - 'c-a = t- ~- rt : I ? .: - g= __.;...__:. : 2-- o __:=a .:,.== - - -

=_. u

.. =_:- =a _. = _... _. _ r-a r N b. .~ _5_ N.. Y....!.I'. _ b.[*.b. '2.b.- bi' ~ . -[.__ ~. : a. O 7 m ~. ~ _ ~ *... -*1.--

== _... ~ . _.j.... ;__ .] "- '.- ~. }. _ g.. . _.. _...__.9_.. y r - _. - ,_ g., _..__g-4-- O ___.*.*J"--*.-*..*: ~.;..= .C.;~.-*--~ J'I 7*- -t= !-

.-.=.177. C : -* * - *..:_-*

~7.-"- -- : : =_j=.:... _=__,r..__._._=_._'_-_ _ _ _.. _. _ _ - T. ::' --- ! T '_- J;;-*. $'.~ *:: ' __"___'.._._-r._; E '. '.. _ t --- b.:.C[. _-----_r [5ki. _.j _ ~ ...b.*:.I** 3bb5_... _.. _.$ 5

jg.-Q:T - = ' = -=d: _f =3: EM-t

- --- - := - -- ;.=.:_ n g :- = = = =

3 -__~_ - T..-...',*.. =.r :. "*:. T : _..-- ~ ~ ~ - - - 22 - t --

• 2*

"*3-- ~ - - - ~2 ' :- ~ [ ':O ' n*tl -."-!~~ w-m h-*-.__ .. ~ ~... .__i---~~.--* -~H . _.,.,,.,. _ _.-- ~~~F-t'-.'.'_' ' ' ~ - --%. ~~~ - . = -d.n._ += -- : r - : =r ;A-g t:.= r-- t .. __ _f:". .. _..... +. _.. =... = _. - _ -. r. .. g... =_ :_ _ . - _ _.__.;::J==::. - l ,. _.= - = r ::_ _ _r =_2 :=t- .c ::. l .___a ._L -.,-...q;;_.._-.--_._,.;_; . 1==5. --- - - -=- _= :_=-_

==.. . = = = = _. _. --- - T_'_. _.... : En.. -_.=.r=

n........, '..-- -- '. T ( -

1 - r:.. ::_m.en:E=. 10 = in. --- -iI5'_f" EFT *_-" + MOD ES 5 & 6 '!:2=== u u- _... - =..... _... _.. t, :.__ _ ..3_.-.._ ::. :._- :: r=. A..t.'n. ! ' ___=_.._._._=.._a.t._:- . = .r 2 :=t_.!--- .c -z___.-_.._. _ = ._ _ g=,_ __u._ p._u \\ '..._ r... _. :~- T... sT.~* ~~~5 ~ j.- .-. YY 55~'ffT~. ~_-4 V~4='5 =~ 6 7 8 9 .10 11 12 i l STORED BORIC ACID CONCENTRATION (WT%) FIGURE 3.1-1 Minimum Boric Acid Storage Tank Volume and Temperature as a Function of Stored Boric Acid Concentration CALVERT CLIFFS - UNIT 1 Amendment No. 27, 48 CALVERT CLIFFS - UNIT 2 3/4 1-15 Amendment No, pl 1 -u

REACTIVITY' CONTROL SYSTEMS BORATED WATER SOURCES - OPERATING ~ LIMITING CONDITION FOR OPERATION 3.1.2.8 At least two of the following three borated water sources shall be OPERABLE: a. Two boric acid storage tank (s) and one associated heat tracing circuit per tank with the contents of the tanks in accordance with Figure 3.1-1 and the baron concentration limited to < 8%, and b. The refueling water tank with: 1. A minimum contained borated water volume of 400,000

gallons, 2.

A beron concentration of betwaen 2300 and 2700 ppm, l 3. A minimum solution temperature of 40'F, and 4. A maximum solution temperature of 100*F in MODE 1. APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: With only one borated water source OPERABLE, restore at least two borated water sources to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours and borated to a SHUTDOWN MARGIN equivalent to at least 3% ak/k at 200*F; restore at least two borated water sources to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours. SURVEILLANCE REQUIREMENTS 4.1.2.8 -At least two borated water sources shall be demonstrated OPERABLE: a. At least once per 7 days by: 1. Verifying the boron concentration in each water source, 2. Verifying the contained borated water volume in each water source, and 3. Verifying the boric acid storage tank solution temperature. b. At least once per 24 hours by verifying the RWT temperature when the outside air temperature is < 40*F. Amendment No. A$, 55 CALVERT CLIFFS - UNIT 1 3/4 1-16 CALVERT CLIFFS - UNIT 2 Amendment No. 37, 38

REACTIVITY, CONTROL SYSTEMS CEA OROP TIME LIMITING CONDITION FOR OPERATION 3.1.3.4 The individual full length (shutdown and control) CEA drop time, from a fully withdrawn position, shall be < 3.1 seconds from when the ll electrical power is interrupted to the CEA~ drive mechanism until the CEA reaches its 90 percent insertion position with: T,yg >_ 515'F, and a. b. All reactor coolant pumps operating. APPLICABILITY: MODES 1 and 2. ACTION: a. With the drop time of any full length CEA determined to exceed the above limit, restore the CEA drop time to within the above limit prior to proceeding to MODE 1 or 2. b. With the CEA drop times within limits but determined at less than i full-reactor coolant flow, operation may proceed provided THERMAL POWER is restricted to less than or equal to the maximum THERMAL POWER level allowable.for the reactor coolant pump combination operating at the time of CEA drop time determinatinn. SURVEILLANCE REQUIREMENTS 4.1.3.4,The CEA drop time of full length CEAs shall be demonstrated through measurement prior to reactor criticality: a. For all CEAs following each removal of the reactor vessel head, b. For specifically affected individual CEAs following any main-tenance on or modification to the CEA drive system which could affect the drop time of those specific CEAs, and c. At least once per 18 months. CALVERT CLIFFS - UNIT 1 3/4 1-23 Amendment No. 32, 39, 55 CALVERT CLIFFS - UNIT 2 Amendment No. 76, 18, 38

.c 4 REACTI'VITY dONTROL SYSTEMS SHUTOOWN CEA INSERTION LIMIT LIMITING CONDITION FOR OPERATION 3.1.3.5 All shutdown CEAs shall be withdrawn to at least 129.0-inches. . I APPLICABILITY: MODES 1 and 2*#. ACTION: With a maximum of shutdown CEA withdrawn, except for surveillance testing pursuant to specification 4.1.3.1.2, to less' than 129.0 inches, I within one hour either: a. Withdraw the CEA to at least 129.0 inches, or l - b. Declare the CEA inoperable and apply Specification 3.1.3.1. SURVEILLANCE REQUIREMENTS 4.1.3.5 Each shutdown CEA shall be determined to be withdrawn to at least 129.0 inches: I a. Within 15 minutes prior.to withdrawal of any CCAs in regulat-ing groups during an approach to reactor criticality, and b. ,At least once per 12 hours thereafter.

• See Special Test Exception 3.10.2.

1. With K,ff,- 1.0 3

4 CALVERT CLIFFS-UNIT 1 Amendment No. 28 CALVERT CLIFFS-UNIT 2 3/4 1-24 Amendment No.13 e-3 -w.. g,*=-gy m _-.-,-..,p -p, ,g- +,

• wy.

,4- - -%,-,,,,,+w,w goo.+w,.e-s,.,e,-,=p-,p,-cp-g-.-e-,-y-=y. ---m.w-gp --cw- ,-,--=-we w.y,s-

POWER' DISTR 130 TION LIMITS-SURVEILLANCE REQUIREMENTS (Continued) T 4.2.2.3 F shall be determined each time a calculation of F is required xy y by using the incore detectors to obtain a power distribution map with i all full length CEAs at or above the Long Term Steady State Insertion Limit for the existing Reactor Coolant Pump combination. This determina-tion.shall be limited to core planes between 15% and 85% of full core height inclusive and shall exclude regions influenced by grid effects. shall be determined each time a calculation of Ffyis required 4.2.2.4 T q and the value of T used to determine F shall be the measured value of q xy q. J CALVERT CLIFFS-UNIT 1 Amendment No. 27, 32 CALVERT CLIFFS-UNIT 2 3/42-7 Amendment No. 9, 18 _,. _L. _ _

~lIIllllllllllllllllll SS 1.00 362,1.00) UNACCEPTABLE 4 OPERATION N E4 m REGION pp ijtiltitititiffittttittittiii r k,, 55 2 )1)'llll.Fhy LIMIT CURVE > 0.90 '.. ( n ~ 59 2 T ~,,' F LIMITCURVE N e 53 ' "4 (1.70,.85) g a 1 %,,IN W 0.80 I g (1.695.775) m e ACCEPTABLE OPERATION 0.70 REGION p o i ff "i 2 @ 0.60 er a t 1 28 o gg -j i _ t. 28 l [~ 0.50 .1L l. I g J P- -"O 1.56 1.58 1.60 1.62 1.64 1.66 1.68 1.70 1.72 Me C:3 T T C:3 FXY fr SS N Figure 3.2-3 TOTAL RADIAL PEAKING FACTORS vs ALLOWABLE FRACTION OF RATED THERMAL POWER s-D r--

3/4.4* REACTOR COOLANT SYSTEM COOLANT LOOPS AND COOLANT CIRCULATION STARTUP AND POWER OPERATION LIMITING CONDITION FOR OPERATION 3.4.1.1 Both reactor coolant loops and both reactor coolant pumps in each loop shall be in operation. APPLICABILITY: MODES I and 2*. ACTION: With less tha. the above required reactor coolant pumps in operation, be in at least HOT STANDBY within 1 hour. 1 [ SURVEILLTNCE REQUIREMENTS 4.4.1.1 lThe above required reactor coolant loops shall be verified to be in operation and circulating reactor coolant at least once per 12 hours. J J i

• See Special Test Exception 3.10.3.

CALVERT CLIFFS - UNIT 1 Amendment No. 55 CALVERT CLIFFS - UNIT 2 3/4 4-1 Amendment No. 38 l l

REACTOR COOLANT SYSTEM COOLANT LOOPS AND COOLANT CIRCULATION HOT STAND 8Y LIMITING CONDITION FOR OPERATION 3.4.1.2 a. The reactor coolant loops listed below shall be OPERABLE: 1. Reactor Coolant Loop #11 (#21) and at least one associated reactor coolant pump.

2. ' Reactor Coolant Loop #12 (#22) and at least one associated reactor coolant pump.

b. At least one of the above Reactor Coolant Loops shall be in operation *. APPLICABILITY: MODE 3 ACTION: a. With less than the above required reactor coolant loops OPERABLE, restore the required loops to OPERABLE status within 72 hours or be in HOT SHUTDOWN within the next 12 hours. b. With no reactor coolant loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and initiate corrective action to return the required loop tp operation within one hour. SURVEILLANCE REQUIREMENTS

4. 4.1. 2.1 At least the above required reactor coolant pumps, if not in operation, shall be determined to be OPERABLE once per 7 days by verifying correct breaker alignments and indicated power availability.

4.4~1.2.2 ' At least one cooling loop shall be verified to be in operation and circulating reactor coolant at least once per 12 hours.

• All reactor coolant pumps may be de-energized for up to 1 hour (up to 2 hours for low flow test) provided (1) no operations are permitted that would cause dilution of the reactor coolant system boron cogcentration, and (2) core outlet temperature is maintained at least 10 F'below saturation temperature.

CALVERT CLIFFS - UNIT 1 Amendment No. AB, 55 CALVERT CLIFFS - UNIT 2 3/4 4-2 Amendment No. 37, 38

REACTOR COOLANT SYSTEM COOLANT LOOCS AND COOLANT CIRCULATION SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.1.3 a. At least two of the coolant loops listed below shall be OPERABLE: 1. Reactor Coolant loop #11 (#21) and its associated steam generator and at least one associated reactor coolant' pump, 2. Reactor Coolant Loop #12 (#22) and its associated steam generator and at least one associated reactor coolant pump,

3. - Shutdown Cooling Loop #11 (#21)*,

4. Shutdown Cooling Loop #12 (#22)*. b. At least one of the above coolant loops shall be in operation **. APPLICABILITY: -MODES 4***# and 5***f. ACTION: a. With less than the above required coolant loops OPERABLE, initiate corrective action to return the required coolant loops to OPERABLE status within u ' hour or be in COLD SHUTDOWN within 24 hours. b. Wi no coolant loop in operation, s'u' spend all operations involving a reduction in boron concentration of the Reactor ~ Coolant System and initiate corrective action to return the required coolant loop to operation within one hour. SURVEILLANCE REQUIREMENTS 4.4.,1.3.1, OPERABLE once per 7 days by verifying correct breaker alignments The required shutdown cooling loop (s), if not in operation, shall be determined and indicated power availability for pumps and shutdown cooling loop valves.

• The normal or emergency power source may be inoperable in MODE 5.

'**All reactor coolant pumps and shutdown cooling pumps may be de-energized for up to 1 hour provided (1) no operations are permitted that would cause dilution of the reactor coolant sy: tem baron concentration, and (2) core outlet temperature is maintained at '6tst 10 F below saturation temperature.

• • • A reactor coolant pump shall nc' us started with one or more of the RCS cold leg temperatures less tm v luas to 275 F unless (1) the pressurizer water volume is less than iu r,J foetorf2)thgsecondarywatertempera-ture of. each steam generato, is, n. than 46 F (34 F when measured by a surface contact instrument) above teach of the RCS cold leg temperatures.

1. See Special Test Exception 3.10.5.

CALVERT CLIFES - UNIT 1 Amendment No. 55 CALVERT CLIFFS - UNI.T 2 3/4 4-2a Amende nt No. 38

REACTbRCOOLANTSYSTEM COOLANT *_^JPS'AND COOLANT CIRCULATION SHUTDOWN SURVEILLANCE IEQUIREMENTS (Continued) 4.4.1.3.2.The required steam generator (s), if it is'being used to meet 3.4.1.3.a. shall be determined OPERABLE by-verifying the secondary side water level to be above -50 inches at least once per 12 hours. 4.4.1.3.3 At least one coolant loop shall be verified to be in operation and circulating reactor. coolant at least once per 12 hours. l 2 CALVEP.i-CLIFFS - UNIT 1 Amendment No. 55 CALVERT CLIFFS - UNIT 2 3/4 4-2b Amendment No. 38 + T-e- y -9 -r = v -e w -e-.*ywmww+==*,9c-- -,vv--www-tv--, -,we- --va-+ --r--g --gmy

3/4.5 EMERGEllCY CORE COOLING SYSTEMS (ECCS) SAFETY INJECTION TANKS LIMITING CONDITION FOR OPERATION a 3.5.1 Each rear +or coolant system safety injection tank shall be OPERABLE with-a. The isolation volve open, b. A contained borated water volume of between 1113 and 1179 cubic feet of borated water (equivalent to tank levels of between 187 and 199 inches, respectively), c. A boron concentration of between 2300 and 2700 ppm, and l d. 'A nitrogen cover-pressure of between 200 and 250 psig. APPLICABILITY: MODES 1, 2 and 3.* ACTION: a. With one safety injection tank inoperable, except as a result of a closed isolation valve, restore the inoperable tank to OPERABLE status within one hour or be in HOT SHUTOOWN within the next 12 hours. b. With one safety injection tank inoperable due to the isolation valve being closed, either immediately open the isolation valve or be in HOT STANDBY within one hour and be in HOT SHUTOOWN within the next 12 hours. SURVEILLANCE REQUIREMENTS A 4.5.1 Each safety injection tank shall be demonstrated OPERABLE: a. At least once per 12 hours by: 1. Verifying the contained borated water volume and nitrogen cover-pressure in the tanks, and 2. Verifying that each safety injection tank isolation valve is open.

• With pressurizer pressure > 1750 psia.

CALVERT CLIFFS - UNIT 1 Amendment No. AB, 55 CALVERT CLIFFS - UNIT 2 3/4 5-1 Amendment No. 37, 38

4 4 EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b. At least once per 31 days by verifying the boron concentration of the safety-injection tank' solution. c. At'least once per 31 days when the RCS pressure is above 2000 psig, by verifying that power to the; isolation valve operator is removed by maintaining the feeder breaker open under administrative control. d. Within 4 hours prior to increasing the RCS pressure above 1750 psia by verifying, via local indication at the valve, that the tank isolation valve is open. At least once per 18 months by' verifying that each safety e. injection tank-isolation valve opens automatically under each of the following conditions: 1. When the RCS pressure exceeds 300 psia, and 2. Upon receipt of a safety injection test signal. f. Within~one hour prior to each increase in solution volume of 1 1% of normal tank volume by.verifyi ration at the operating high pressure sa,ng the boron concent-fety injection pump . discharge is between 2300 and 2700 ppm. 2 4 CALVERT CLIFFS - UNIT 1 3/4 5-2 AmendmentNo.//,55 CALVERT CLIFFS - UNIT 2 Amendment No. 31, 33

~ EMERGE'NCY CORE COOLING SYSTEMS ECCS SUBSYSTEliS - T < 300'F avg LIMITING CONDITION FOR OPERATION 3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERABLE: One# OPERABLE high-pressure safety injection pump, and l -a. b. An OPERABLE flow path capable of taking suction from the refueling water tank on a Safety Injection Actuation Signal and automatically transferring suction to the contain-ment sump on a Recirculation Actuation Signal. APPLICABILITY: MODES 3* and 4. ACTION: a. With no ECCS subsystem OPERABLE, restore at least one ECCS subsystem to OPERABLE status within 1 hour or be in COLD SHUTOOWN within the next 20 hours. b. In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission persuant to Specification 6.9.2 within 90 days describing the t bcumstances of the actuation and the total accumulated actuation cycles to date. SURVEILLANCE REQUIREMENTS

4. 5. 3.1 The ECCS subsystem shall be demonstrated OPERABLE per the applicable l Surveillance Requirements of 4.5.2 4.5.3;2 All high-pressure safety injection pumps, except the above required OPERABLE pump, shall be demonstrated inoperable at least once per 12 hours whenever the temperature of one or more of the RCS cold legs is 1 275*F by verifying that the motor circuit breakers have been removed from their electrical p >wer supply circuits.

i

• With pressurizer pressure < 1750 psia.

1. A maximum of one high-pressure safety injection pump shall be CPERABLE whenever the temperature of one or more of the RCS cold legs is 1 275 F.

CALVERT CLIFFS - UNIT 1 3/4 5-6 Amendment No.34 CALVERT CLIFFS - U: LIT 2 Amendaent Jo,16

EMERGENCY CORE COOLING SYSTEMS REFUELING WATER TANK LIMITING CONDITION FOR OPERATION 3.5.4 The refueling water tank shall be OPERABLE with: a. A minimum contained borated water. volume of 400,000 gallons, tu A boron concentration of between 2300 and 2700 ppm, l c. A' minimum water temperature of 40*F, and d. A maximum solution temperature of 100*F in MODE 1. APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: With the refueling water tank inoperable, restore the tank to OPERABLE status within 1 hour or be in at least HOT STANDBY within 6 hours and in COLD SHUTDOWN within -the following 30 hours. SURVEILLANCE REQUIREMENTS 4.5.4 The RWT shall be demonstrated OPERABLE: a. ' At least once per 7 days by:

1.

Verifying the contained barated water volume in the tank, and 2. Verifying the boron concentration of the water. b. At least once per 24 hours by verifying the RWT temperature when the outside air temperature is < 40*F. CALVERT CLIFFS - UNIT 1 3/4 5-7 Araendment No./2, 55 CALVERT CLIFFS - UdIT 2 Amend.. ant ::o. 37, 38 . ~.

PLANT SYSTEMS 3/4.7.8 HYDRAULIC SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.8.1 All hydraulic snubbers listed in Table 3.7-4 shall be OPERABLE. APPLICABILITY: MODES 1, 2, 3 and 4. ACTION: With_one or more hydraulic snubbers inoperable, replace or restore the inoperable snubber (s) to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. SURVEILLANCE REQUIREMENTS 4.7.8.1 Hydraulic snubbers shall be demonstrated OPERABLE by performance of the following augme.ited inservice inspection program and the requirements of Specification 4.0.5. -a. Each hydraulic snubber with seal material fabricated from ethylene propylene or other materials demonstrated compatible with the operating environment and approved as such by the NRC, shall be determined OPERABLE at least once after not less than 4 months but within 6 months of initial criticality and in ac-cordance with the inspection schedule of Table 4.7-4 thereafter, by a visual inspection of the snubber. Visual inspections of the snubbers shall include, but are not necessarily limited to, in-spection of the hydraulic fluid reservoirs, fluid connections, and linkage connections to the piping and anchors. Initiation of the table 4.7

• inspection schedule shall be made assuming the unit was previously at the 6 month inspection interval.

b. Each hydraulic snubber with seal material not fabricated from ethylene propylene or other materials demonstrated compatible with the operating environment shall be determined OPERABLE at least once per 31 days by a visual inspection of the snubber. Visual inspections of the snubbers shall include, but are not necessarily limited to, inspection of the hydraulic fluid re-servoirs, fluid connections, and linkage connections to the piping and anchors. CALVERT CLIFFS-UNIT 1 3/4 7-25 ) CALVERT CLIFFS-UNIT 2 Amendment No. 10 .}

PLANT SYSTEMS-4 SURVEILLANCE; REQUIREMENTS (Continued). 4 c.' l At least once per l'8 months during shutdown, a representative sample of at'least 10 hydraulic snubbers or at least 10% of - all snubbers. listed in Table 3.7-4, whichever is less,. hall be selected _and functionally tested to verify correct pistoa . movement, lock up and bleed. Snubbers greater than 50,000 lb. capacity may be excluded from functional testing requirements. Snubbers selected for functiontl testing shall be selected on a-rotating basis.u. Snubbers identified as either "Especially Difficult to Remove" or in "High Radiation Zones" may be' exempted from functional testing provided these snubbers were . demonstrated OPERABLE during. previous functional tests.. Snubbers found inoperable'during functional testing shall be. restored-to OPERABLE status prior to resuming operation. For each snubber ~ found inoperable during these functional tests, an additional minimum of 10% of all snubbers or 10 snubbers, whichever-is . less, shall also be functionally tested until no more. failures are found or all snubbers have been functionally tested. d. Snubbers served by a common hydraulic reservoir are indicated I by a' bracket in Table 2.7-4. All reservoirs ' serving more-than ore snubber-shall be inspected to ensure adequate hydraulic level: 1. Within 7 days '.fter reactor startup'following a major outage or following any maintenance in the immediate vicinity of these snubbers, reservoirs or associated hydraulic piping; and-2. Every 31 days + 25 percent. J t i i CALVERT CLIFFS-UNIT 1 3/4 7-26 Amendment No. 55 CALVERT CLIFFS-UNIT ~2 Amendment No. 70,38 ~4,.._..,, ...e .-.m .,__,m,.,,,vv.-- .-ww,ww,,,,w,-_, ,...,-,,.m_,y.,,%,- m-,,m-y,. ,,,w,,m,, - _,yo9.,,v.%..-., ..,3-,,,y__--..,,,,,,,c

9 TABLE 3.7-4 SAFETY RELATED HYDRAULIC SNUBBERS

• P M

i U-SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFIC" ULT c-NO. ON,' LOCATION AND ELEVATION INACCESSIBLE ZONE ** TO REMOVE' } -(A or I) (Yes or No) (Yes or No) 2-61-19 CONT. SPRAY HDR FOR SPRAY RING

1. 22 39' I

'Yes Yes 2-63-1 S/G #22 BLOWDOWN LINE 34' 11' A No No ] 2-63-2 S/G #22 BLOWDOWN LINE 27' 10' A No No-2-63-3 . NITROGEN LINE TO S/G #22 77'6" .I 'Yes No 4 2-63-4 NITROGEN LINE TO S/G #22 77'6" I Yes No w i 2 j 7 2-63-5 S/G #21 SURFACE BLOWDOWN LINE 76'9" I Yes No 2-63-6 S/G #21 SURFACE BLOWDOWN LINE 76'9" I Yes No 2-63-11 STEAM GENERATOR #21 75' I Yes Yes l ) l 2-63-12 STEAM GENERATOR #21 75' I Yes Yes 2-63-13 STEAM GENERATOR #21 75' I Yes Yes 2-63-14 STEAM GENERATOR #21 75' I Yes Yes 4 2-63-15 STEAM GENERATOR #21 75' I Yes Yes E 2-63-16 STEAM GENERATOR #21 75' I Yes Yes Ei i 2-63-17 STEAM GENERATOR #21 75' I Yes Yes l E L ,~ CD

TABLE 3.7-4 c. O SAEETY RELATED HYDRAULIC SNUBBERS

• b SNUBRr's SYSTEM SNUBBER INSTALLED ACCESSIBLE OR llIGil RADI ATION ESPECIALLY DIFFICULT C

NO. ON, LOCATION AND ELEVATION .lNACCESSIBLE ZONE ** TO REMOVE-4", (A-or 1) __ (Yes or No) (Yes or No) si 2-63-18 STEAM GENERATOR #21 75'-- I I Yes Yes G 2-63-19 STEAM GENERATOR #22 75' I Yes -Yes m 2-63-20 STEAM GENERATOR #22 75' I Yes Yes 2-63-21 STEAM GDNERATOR #22 75? I Yes Yes 2-63-22 STEAM GENERATOR #22 75' I Yes Yes u, 1 2-63-23 STEAM GENERATOR #22 75' I Yes Yes y E 2-63-24 STEAM GENERATOR #22 75' I Yes Yes 2-63-25 STEAM GENERATOR #22 75' I-Yes Yes 2-63-26 STEAM GENERATOR #22 75' I Yes Yes E 2-64-1 PRESSURIZER REL PIPING UPSTREAM MOV 403 111'6" I Yes No [ 2-64-2 PRESSURIZER REL PIPING TO RV 200 y 79'11" I. Yes No l 2-64-3 PRESSURIZER REL PIPING DOWtlSTREAM l MOV 405 84'3" I-Yes No ? m i i

I

h$

r TABLE 3.7-4 Si SAFETY RELATED HYDRAULIC SNUBBERS

• c, E:

4 SNUBBER SYSTEM SNUBBER INSTALLED. >.CLESSIBLE OR T' NO. 6N, LOCATION AND ELEVATION INACCESSIBLE ' HIGH RADIATION ESPECIALLY DIFFICul.T ZONE ** TO REMOVE . EE (A or I) (Yes or No) (Yes or No) 2-838-2 MSIV #21 HYDRAULIC SUPPLY 27' A No No 1 2-838-3 MSIV #21 HYDRAULIC RETURN 27' A No No l 3 j{

• Snubbers may be added to safety related systems without prior License Amendment to Table 3.7-4 provided that a revision to Table 3.7-4 is included with the next License Amendment request.

[n

• • Modifications to this table due to changes in high radiation areas sh611 be submitted to the NRC as-4 part of the next License Amendment request.

N a Et a n f kU S$ i i i ) 1 j I

52 . EE TABLE 4.7-4 9 HYDRAULIC SNUBBER INSPECTION SCHEDULE UI NUMBER OF SNUB 8ERS F004D IN0PERABLE NEXT. REQUIRED jg. DURING INSPECTION OR DURING INSPECTION INTERVAL *. INSPECTION INTERVAL ** M 0 18' months + 25% 1 12 months T 25% 2 6 months i 25%- 3 or 4 124 days-T 25% 5, 6, or 7 62 days T 25% >8 31 days i25% R a 7'W

• Snubbers may be categorized into two groups, " accessible" and " inaccessible" This categorization shall be based upon the snubber's accessibility for inspection during reactor operation..These two groups may be inspected independently according to the'above ~ schedule.
  • The required inspection interval shall'not be lengthened more than one step at a time.

P I a k

REFUEtING OPERATIONS CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING LIMITING CONDITION FOR OPERATION 3.9.7 Loads in excess of 1600 pounds shall be prohibited from travel over fuel assemblies in the storage pool. APPLICABILITY: 'With fuel assemblies in the storage pool. ACTION: ~ With.the requirements of the above specification not satisfied, place the crane lead in a safe condition. The provisions of Specification 3.0.3 are applicable. 4 SURVEILLANCE REQUIREMENTS-4.9.7 The weight of'each load, other than a fuel assembly and CEA, ~ -shall be verified to be < 1600 pounds prior to moving it over fuel assemblies. i CALVERT. CLIFFS - UNIT 1 g E CALVERT CLIFFS UNIT 2 3/4 9-7 .,c ,,.,,,~,,m.-.... .,,,,,...,,,,__,._u.,.,y_~_,my,_._,,,,,,..,,.,m.-m_.., ,,m..,.m.,

REFUELING OPERATIONS-SHUTDOWN COOLING AND'C00LANT CIRCULATION LIMITING CONDITION FOR OPERATION 3.9.8.l' At least one shutdown cooling loop shall be in operation.* I APPLICABILITY: MODE 6 at all reactor water levels. l ACTION: a. Wich less than one shutdown cooling loop in operation, suspend all operations involving an increase in the reactor decay heat load or a reduction in baron concentration of the Reactor Coolant System. Close all containment penetrations providing direct access f,om the containment atmosphere to the outside-atmosphere witnin'4 hours. The shutdown cooling pumps may be de-energized curing the time intervals required for local leak rate testing of containment penetration number 41 pursuant to the_ requirements of Specification 4.6.1.2.d and/or to permit maintenance on valves located in the common shutdown cooling suction line, provided (1) no operations are permitted which could cause dilution of.the reactor coolant system boron concentration, (2) all CORE ALTERATIONS are-susoended. (3) all E containment penetrations providing direct access from the containment atmosphere to the outside atmosphere are maintained s'ased, and (4) the w2'.ar level above the top of the irradiated L Lis greater than 23 feet. b. The provisions of Specification 3.0.3 are not applicable. SURVEILLANCE REQUIREMENTS 4.9.8.1 ~ A shutdown cooling loop-shall be determined to be in operation and circulating reactor coolant at a flow rate of > 3000 gpm** at least once per 4 hours. J

• The shutdown cooling loop may be removed from operation for up to 1 hour per 8 hour period during the performance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs.
  • > 1600 gpm when the Reactor Coolant System is drained to a level below the midplane of the hot leg.

CALVERT CLIFFS - UNIT 1 Amendment No. 38, 55 CALVERT CLIFFS - UNIT 2 3/4 9-8 Amendment No. 37, 38 11

( REFUELING OPERATIONS ' SHUTDdWNCOULINGANDCOOLANTCIRCULATION LIMITING CONDITION FOR OPERATION 3.9.8.2 Two ~ (2) independent shutdown cooling loops shall be OPERABLE *#. APPLICABILITY:. Mode 6 when the water ' level above the top of the. irradiated fuel assemblies seated within the reactor pressure vessel is less than 23 feet. ACTION: a. With less than the required shutdown cooling loops OPERABLE, initiate corrective action.to return loops to OPERABLE status within one hour. b. The provisions of Specification 3' 0.3 are not applicable. 4 SURVEILLANCE REQUIREMENTS 4.9.8'.2 No additional Surveillance Requirements other than those reqJired by Specification 4.0.5. a r

• Normal or emergency power source may be inoperable for each shutdown cooling loop.

1. 0ne shutdown cooling loop may be replaced by one spent fuel pool cooling loop

~ when it is lined up to provide cooling flow to the irradiated fuel in the reactor core and the' heat generation rate of the. core is below the heat ~ removal capacity of the spent fuel pool cooling loop. CALVERT CLIFFS - UNIT 1 Amendment No. 55 CALVERT CLIFFS - UNIT 2 3/4 9-8a Amendment No.'38 w-ee

• e-p-

w y -e e-s-e 9 r w', 9 esc-9 9m-> aw y. g w-% -hw-- = %g --m+--e

3/4.15 SPECIAL TEST EXCEPTIONS SHUT 00WN MARGIN LIMITING CONDITION FOR OPERATION 3.10.1 The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 may be suspended for measurement of CEA worth-and' shutdown margin provided reactivity egnivalent to at least the highest estimated CEA worth is available for : rip insertion from OPERABLE CEA(s). APPLICABILITY: MODE 2. ACTION: With any full length CEA not fully inserted and with less than. a. the above reactivity equivalent available for trip insertion, immsdiately initiate and continue boration at > 40 gpm of 2300 l ppm boric acid solution or its equivalent untiT the SHUTDOWN MARGIN required by Specification 3.1.1.1 is' restored. b. With all full length CEAs inserted and the reactor subcritical by less than the above reactivity equivalent, immediately initiate and continue boration at 1 40 gpm of 2300 ppm boric l acid solution or its equivalent until the SHUTOOWN MARGIN re-quired by Specification 3.1.1.1 is restored. SURVEILLANCE REQUIREMENTS 4.10.1.1 The position of each full length CEA required either partially or fully withdrawn shall be determined at least once per 2 hours. 4.10.1.2 'Each CEA not fully inserted shall be demonstrated capable of full insertion when tripped from at least the 50% withdrawn position with-in 24 hours prior to reducing the SHUTDOWN MARGIN to less than the limits of Specification 3.1.1.1. CALVERT CLIFFS - UNIT 1 3/4 10-1 Amendment No. 3E,48 Mendment.10. N, 31 CALLG CLIFFS - J:!IT 2

SPECIAL TEST EXCEPTIONS MODERkTORTEMPERATURECOEFFICIENT,CEAINSERTIONANDPOWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION 3.10.2 The moderator temperature coefficient, the CEA insertion and the power-distribution limits of Specifications 3.1.1.4, 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.2, 3.2.3, and 3.2.4 may be suspended during the performance of PHYSICS TESTS provided: a. The THERMAL POWER is restricted to below 85% of RATED THERMAL-POWER, and b. The limits of Specification 3.2.1 are maintained and determined as specified'in Specification 4.10.2.2 below. APPLICABILITY: MODES 1 and 2. ACTION: With any of the limits of Specification 3.2.1 being exceeded while the require-mer.ts of Specifications 3.1.1. 4, 3.1. 3.1, 3.1. 3. 5, 3.1. 3. 6, 3.2.2, 3.2. 3 and 3.2.4'are suspended, either: Reduce THERMAL POWER sufficiently to satisfy.-the require-a. ments of Specification 3.2.1, or b. Be in HOT STANDBY within 6 hours. SJ.lVEILLANCE REQUIREMENTS 4.10.2.1 The THERMAL F0WER shall be determined at least once per hour during PHYSICS TESTS in which the requirements of Specifications 3.1.1.4, 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.2, 3.2.3 or 3.2.4 are suspended and shall be verified to be within the test power plateau. l 4.10.2.2 ' 'The linear heat rate shall be determined to be within the limits of Specification 3.2.1 by monitoring it continuously with the Incore Detector Monitoring System pursuant to the requirements of Specifications 4.2.1.3 and 3.3.3.2 during PHYSICS TESTS above 5% of RATED THERMAL POWER in which the requirements of Specifications 3.1.1.4, 3.1.3.1 3.1.3.5, 3.1.3.6, 3.2.2, 3.2.3 or 3.2.4 are suspended. CALVERT CLIFFS - UNIT 1 Amerdment No. 27, 55 CALVERT CLIFFS - UNIT 2 3/4 10-2 Amendment No. 38 nc- --r 1----- ~ r - - -- -, - - ~

1 l ~ 3/4.2 POWER DISTRIBUTION LIMITS BASES 3 /4. 2.-l LINEAR HEAT RATE The limitation on linear heat rate ensures that in the event of a LOCA, the peak temperature of the fuel cladding will not exceed 2200*F. Either of the two core power _ distribution monitoring systems, the Excore Detector Monitoring' System and the Incore Detector Monitoring System, provide adequate monitoring of the core power distribution and are capable of verifying that the linear heat rate does not exceed its limits. The Excore Detector Monitoring System performs' this -function by continu-ously monitoring the AXIAL SHAPE INDEX with the OPERABLE quadrant symmetric excore neutron flux detectors and verifying that the AXIAL SHAPF INDEX is maintained within the allowable limits of Figure 3.2-2. In conjunction with the use of.the excore monitoring system and in establishing the AXIAL SHAPE INDEX limits, the following assumptions are made:

1) the CEA insertion limits of Specifications 3.1.3.5 and 3.1.3.6 are satisfied, 2) the flux peaking augmentation factors are as shown in Figure 4.2-1, 31 the AZIMUTHAL POWER TILT' restrictions of Specification 3.2.4 are satisfied, and

4) the TOTAL PLANAR RADIAL PEAKING FACTOR does not exceed the limits of Specification 3.2.2.

The Incore Detector Monitoring System continuously provides a direct measure of the peaking factors and the alarms which have been establi5hed for. the individual incore detector segments ensure that the peak linear heat rates will be maintained within the allowable limits of Figure 3.2-1. The setpoints for these alarms include 1110wances, set in the conservative ~ directions, for 1) flux peaking augmenta+. ion factors as shown in Figure 4.2-1, 2) a measurement-calculational uncetainty factor of 1.070, 3) an l engineering uncertainty factor of 1.03, 4) an allowance of 1.01 for axial l fuel densification and thennal expansion, and 5) a THERMAL POWER measurement j uncertainty factor of 1.02. 3/4.2.2. 3/4.2.3 and 3/4.2.4 TOTAL PLANAR AND INTEGRATED RADI AL PEAKING FACTORS - Fh AND F AND AZIMUTHAL POWER TILT - T T 7 q T The limitations on F and T are provided to ensure that the assump-Y tions used in the analysis for eslablishing the Linear Heat Rate and Local Power Density - High LCOs and LSSS setpoints remain valid during operation af the various allowable CEA group insertion limits. The limitations on l and T are provided to ensure that the assumptions used in r q l

ALVtiRT CLIFFS - UNIT 1 B 3/4 2-1 Amendment No. 33, 39

ALVERT CLIFFS - UNIT 2

.ucadacnt :.o. JB, 24 l-l l ~

POWER DISTRIBUTION LIMITS BASES the analysis establishing the DNB Margin LCO, and Thermal Margin / Low Pressure LSSS setpoints remain valid duringT per9 tion at the various o allowable CEA group insertion limits. If F F or T exceed their basic limitations, operation may continue ubr [he ad81tional restric-tions imposed by the ACTION statements since these additional restric-tions provide adequate provisions to-assure that the assumptions used in establishing the Lir. ear Heat Rate, Thermal _ Margin / Low Pressure and Local Power Density - High LCOs and LSSS setpoints remain valid. An AZIMUTHAL POWER TILT > 0.10 -is not expected l and if it should occur, sub-sequent operation would be restricted to only those operations required to identify:the cause of this unexpected tilt. T

1. 7 (1 + T )-

that must be used in the equation F*Y =F JhevalueofT 9 r (1+T ) is the measured tilt. t and F =F q r ~ T T The surveillance requirements for verifying that F p and TTqffe r within their limits provide assurance that the actua1 v Yues fp and T do not exceed the assumed values. Verifying F and F af b p T each 9uel loading prior to exceeding 757, of RATED THENL POWfa provides additional assurance'that the core was properly loaded. J 3/4.2.5 ~DNB PARAMETERS The limits on the DNB related parameters assure'that each of the parameters are maintained within the normal steady state envelope of I operation assumed in the transient and accident analyses. The limits are. !~ consistent with the safety analyses assumptions and have been analytically l, demonstrated adequate to maintain a minimum DNBR of 1.195 throughout each analyzed'trans';nt. l-l The 12 hour periodic surveillance of these parameters through instru-ment readout;is sufficient to ensure that the parameters are restored i- 'within their limits following load changes and other expected transient I operation. The 18 month periodic measurement of the RCS total flow rate l is adequate'to' detect flow degradation and ensure correlation of the l flow indication channels with measured flow such that the indicated percent flow will provide sufficient verification of flow rate on a 12 hour basis. l CALVERT CLIFFS - UNIT 1 8 3/4 2-2 Amendment No. 33, pg, 55 CALVERT CLIFFS - UNIT 2 Amendment No. 78, 37, 38 i

3/4.4 REACTOR COOLANT SYSTEM BASES. 3/4.4.1 COOLANT LOOPS AND COOLANT CIRCULATION The plant is designed to operate with both reactor coolant loops and associated reactor coolant pumps in operation, and maintain DNBR above 1.195 l during all normal operations and anticipated transients. A single reactor coolant loop with its steam generator filled above the low level trip setpoint provides sufficient heat removal capability for core cooling while in MODES 2 and 3; however, single failure considerations require plant shutdown if component repairs and/or corrective actions cannot be made within the allowable out-of-service time. In MODES 4 and 5, a single reactor coolant loop or shutdown cooling loop provides sufficient heat removal capability for removing decay heat; but single failure considerations require that at least two loops be OPERABLE. Thus, if the reactor coolant loops are not OPERABLE, this specification requires two shutdown cooling loops.to be 0PERABLE. The operation of one Reactor Coolant Pump or one shutdown cooling pump provides adequate flow to ensure mixing, prevent. stratification and produce gradual reactivity changes during boron concentration reductions in the Reactor Coolant System. The reactivity change rate associated with boron reductions will, therefore, be within the capability of operator recognition and control. The restrictions on starting a Reactor Coolant Pump during MODES 4 and 5 with one or more _RCS cold legs 1275 F are provided to prevent RCS pressure transients, caused by energy additions from the secondary system, which could exceed the limits of Appendix G to 10 CFR Part 50. The RCS' will be protected against overpressure transients and will not exceed the limits of Appendix G by either (1) restricting the water volume-in the pressurizer and thereby providing a volume for the primary coolant to expand into or (2) by restrict-ing starting of the RCPs to wheg the gecondary water temperature of each steam generator is less than 46 F (34 F when measured by a surface contact instrument) above the coolant temperature in the reactor vessel. 3/4.4.2 SAFETY VALVES The pressurizer code safety valves operate to prevent the RCS from being pressurized above igs Safety Limit of 2750 psia. Each safety valve is designed to relieve 7.6 x 10 lbs per hour of saturated steam at the valve setpoint. The relief capacity of a single safety valve is adequate to relieve any overpressure condition which could occur during shutdown. In the event that no safety valves are OPERABLE, an operating shutdown cooling loop, connected to the RCS, provides ove; pressure relief capability and will prevent RCS overpressurization. During operation, all pressurizer code safety valves must be OPERABLE to prevent the RCS from being pressurized above its safety limit of 2750 psia. The combined relief capacity of these valves is sufficient to CALVERT CLIFFS - UNIT 1 Amendment No. 34, 53, 55 CALVERT CLIFFS - UNIT 2 B 3/4 4-1 Amendment No. 78, 36, 38 ~.-.

REACTOR COOLANT SYSTEM BASES limit the Reactor Coolant System pressure to within its Safety Limit of 2750 psia following a complete loss' of turbine generator load while operat-ing at RATED THERMAL POWER and assuming no _ reactor trip until the first-Reactor Protective System trip setpoint (Pressurizer Pressure-High) is reached (i.e., no. credit is taken for a direct reactor trip on the loss of turbine) and also assuming no operation of the pressurizer power operated relief valve or steam dump valves.. Demonstration of the safety valves' lift settings will occur only during shutdown and will be performed in accordance with the provisions of Section XI of the ASME Boiler and Pressure Vessel Code. 3/4.4.3 RELIEF VALVES The power operated relief valves (PORVs) operate to relieve RCS pressure below the setting of the pressurizer code safety valves. These relief valves have remotely operated block valves to provide a positive shutoff capability should a relief valve become. inoperable. The electrical power for both the relief valves and the block valves is capable of being supplied from an emergency power source to ensure the ability to seal this possible RCS leak- ~ age path. 3/4.4.4 PRESSURIZER.- A steam bubble in the pressurizer with the level as programmed ensures that the RCS is not a. hydraulically solid system and is capable of accommo-dating pressure surges during operation. The programmed level also protects the pressurizer code safety valves and power operated relief valve against water relief. The power operated relief valves function to relieve RCS pressure during all design transients. Operation of the power operated relief valve in conjunction with a reactor trip on a Pressurizer--Pressure-High signal, minimizes the undesirable opening of the spring-loaded pressurizer code safety valves. The requirement.that 150 kw of pressurizer heaters and their associated controls be capable of being supplied electrical power from an emergency bus provides assurance that these heaters can be energized during a loss of off-site power condition to maintain natural circulation at H0T STANDBY. 3/4.4.5 STEAM GENERATORS The Surveillance Requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS will be maintained. The program for inservice inspection of steam generator tubes is based on a modification of Regulatory Guide 1.83, Revision 1. Inservice inspection of steam generator tubing is essential in order to CALVERT CLIFFS - UNIT 1 B 3/4 4-2 Amendment No. M, 53 CALVERT CLIFFS - UNIT 2 Amendment No. M, 36

~ l 3/4.9 REFUELING OPERATIONS BASES 3/4.9.1 B0RON' CONCENTRATION' The limitations on minimum boron concentration (2300 ppm) ensure that: l 'l) the reactor will remain subcritical during CORE ALTERATIONS, and 2) a uniform baron concentration is maintained for reactivity control in the water volumes having direct access to the reactor vessel. The limitation on K . of no greater than 0.95 which includes a conservative allowance for ~ u8[$rtainties, is sufficient to prevent reactor criticality during refueling operations. 3/4.9.2: INSTRUMENTATION . The OPERABILITY of the source range neutron flux monitors ensures that redundant monitoring capability is available to detect changes ir. the reactivity condition of the core. 3/4.9.3 DECAY TIME The minimu:n requirement for reactor subcriticality prior to movement of irradiated fuel assemblies in the reactor pressure vessel ensures that sufficient time has elapsed to allow the radioactive decay of the short lived fission products. This decay time is cons-istent with the assumptions used in the accident analyses. 3/4.9.4 CONTAINMENT PENETRATIONS The requirements on containment penetration closure and OPE'RABILITY ensure that a release of radioactive material wi* hin containment will be restricted from leakage to the environment. The OPERABILITY and closure restricti'ons are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressur.- ization potential while in the REFUELING MODE. 3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling station personnel can be prorrptly informed of significant changes in the facility status or core reactivity condition during CORE ALTERATIONS. CALVERT .IFFS - UNIT 1 B 3/4 9-1 Amendment No. 48 CALVERT CLIFFS - U::IT 2 Aucndacnt fio. 31 v ~ ' go w-y-eme--ar - - -,a 9.- ww -f--y y

g. wg g - p

,.Ww

• ---py gy ggwp y--*

w=rvg 91+.-p-wprw,.g.-r, yy--gy y--ww-yv,,r---we,, y-gym.i-e+.ww-,9-

4 REFUELING OPERATIONS BASES' 3/4.9.6 REFUELING MACHINE OPERABILITY The OPERABILITY requirements for the refueling machine ensure that: (1) the refueling machine will be used for movement of CEAs and fuel assemblies,- (2) the refueling machine has sufficient load capacity to lift a CEA or fuel assembly, and (3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations. 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING The restriction on movement of loads in excess of the nominal weight of a fuel assembly and CEA over other fuel assemblies in the storage pool ensures that in the event this load is dropped (1) the activity release will be limited to that contained.in a single fuel a.,embly, and (2) any possible distortion. of fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity release assumed in the accident analyses. 3/4.9.8 COOLANT CIRCULATION-The requirement that at least one shutdown cooling loop be in operation ensures that (1) sufficient cooling capacity is available to regove decay heat and maintain the water in the reactor pressure vessel below 140 F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification. The requirement to have two shutdown cooling loops OPERABLE wnc' there is less than 23 feet of water above the core ensures that a single fai'.ure of the operating shutdown cooling loop will not result in a complete loss of decay heat removal capability. With the reactor vessel head removed and 23 feet of water above the core, a large heat sink is available for core cooling, thus in the event of a failure of the operating shutdown cooling loop, adequate time is provided to initiate emergency procedures to cool the core. 3/4.9.9' CONTAINMENT PURGE VALVE ISOLATION SYSTEM The OPERABILITY of this system ensures that the containment purge valves will be automatically isolated upon detection of high radiation levels within the containment. The OPERABILITY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment. CALVERT CLIFFS - UNIT 1 Amendment No. 55 CALVERT CLIFFS - UNIT 2 B 3/4 9-2 Amendment No. 38 t- --,,..-,,ym-., +.y ., - -,,. -,, ~., -}}