Text

Amends 17 & 7 to Licenses NPF-35 & NPF-52,respectively, Modifying Tech Specs to Permit Installation of Boron Dilution Mitigation Sys
	ML20215N176
Person / Time
Site:	Catawba
Issue date:	10/24/1986
From:	Jabbour K; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20215N177	List: ML20215N176; ML20215N181;
References
	NUDOCS 8611040399
	Download: ML20215N176 (22)
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NUCLEAR REGULATORY COMMISSION h

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DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE, INC.

DOCKET NO. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE I

Amendment No. 17

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License No. NPF-35

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1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment to the Catawba Nuclear Station, Unit 1 (the facility) Facility 0perating License No. NPF-35 filed by the Duke

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Power Company acting for itself, North Carolina Electric Membership Corporation and Saluda River Electric Cooperative, Inc., (licensees) 4 dated June 6, 1986, and supplemented September 9, 1986, complies with i

the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Comission; C.

There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; E.

The issuance of this aneendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

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2.

Accordingly, the license is hereby amended by page changes to the Technical i

Specifications as indicated in.the attachments to this license amendment and i

Paragraph 2.C.(2) of Facility Operating License No. NPF-35 is hereby amended l-to read as follows:

(2) Technical Specifications and Environmental Protection Plan

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i The Technical Specifications contained in Appendix A, as revised through Arendment No.17, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are i

hereby incorporated into this license.

Duke Power Company shall i

operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, j

3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 4

\\S Kahtan Jabbo~ r, Project Manager u

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-PWR Project Directorate No. 4 Division of PWR Licensing-A

Attachment:

Technical Specification Changes Date of Issuance:

October 24, 1986 i

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DUKE POWER COMPANY NORTH CAROLINA MUNICIPAL POWER AGENCY N0. 1 PIEDMONT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 7 License No. NPF-52 1.

The Nuclear Regulatory Comission (the Commission) has found that:

A.

The application for amendment to the Catawba Nuclear Station, Unit 2 (the facility) Facility Operating License No. NPF-52 filed by the Duke Power Company acting for itself, North Carolina Municipal Power Agency No. 1 and Piedmont Municipal Power Agency, (licensees) dated June 6, 1986, and supplemented September 9, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Comission; C.

There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; 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.

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. 2.

Accordingly, the license is hereby amended by page changes to the Technical 1

Specifications as indicated in the attachments to this license amendment and i

Paragraph 2.C.(2) of Facility Operating License No. NPF-52 is hereby arrended to read as follows:

(2) Technical Specifications _ _and Environmental Protection Plan I

.The Technical Specifications contained in Appendix A, as revised through Amendment No. 7, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.

Duke Power Company shall j

operate the facility in accordance with the Technical Specifications and the Environniental Protection Plan.

4 l

3.

This license amendnent is effective as of its date of issuance.

1 FOR THE NUCLEAR REGULATORY COMMISSION WT Kahtan Jabbour, Project Manager i

PWR Project Directorate fio. 4 Division of PWR Licensing-A

Attachment:

j Technical Specification Changes i

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Date of Issuance: October 24, 1986 1

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ATTACHMENT TO LICENSE AMENDMENT N0. 17 FACILITY OPERATING LICENSE N0. NPF-35 DOCKET N0. 50-413 AND TO LICENSE AMENDMENT NO. 7 FACILITY OPERATING LICENSE NO. NPF-52 DOCKET N0. 50-414 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.

Amended Overleaf Page Page 3/4 1-2 3/4 1-1 3/4 1-3 3/4 1-4 3/4 3-2 3/4 3-1 3/4 3-12 3/4 3-11 3/4 3-92a 3/4 3-92b 3/4 9-1 3/4 9-la 3/4 9-lb 3/4 9-2 B 3/4 3-7 8 3/4 9-1 B 3/4 9-2 e

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3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL SHUTDOWN MARGIN - T,

>200 F LIMITING CONDITION FOR OPERATION 3.1.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.3% Ak/k for four loop operation.

APPLICABILITY:

MODES 1, 2*, 3, and 4.

ACTION:

With the SHUTDOWN MARGIN less than 1.3% ok/k, immediately initiate and continue boration at greater than or equal to 30 gpm of a solution containing greater than or equal to 7000 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored.

SURVEILLANCE REQUIREMENTS 4.1.1.1.1 The SHUTDOWN MARGIN shall be determined to be greater than or equal to 1.3% ak/k:

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after detection of an inoperable control rod (s) and a.

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at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter while the rod (s) is inoperable.

If the inoperable control rod is immovable or untrippable, the above required SHUTDOWN MARGIN shall be verified acceptable with an increased allowance for the withdrawn worth of the immovable or untrippable control rod (s);

b.

When in MODE 1 or MODE 2 with K,ff greater than or equal to 1 at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that control bank withdrawal is within the limits of Specification 3.1.3.6; When in MODE 2 with K,ff less than l', within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to c.

achieving reactor criticality by verifying that the predicted critical control rod position is within the limits.of Specification 3.1.3.6; d.

Prior to initial operation above 5% RATED THERMAL POWER after each fuel loading, by consideration of the factors of Specification 4.1.1.1.le. below, with the control banks at the maxim ~um inservice limit of Specification 3.1.3.6; and

See Special Test Exceptions Specification 3.10.1.

CATAWBA - UNITS 1 & 2 3/4 1-1

j REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) i When in MODE 3 or 4, at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by consideration of e.

the following factors:

1)

Reactor Coolant System boron concentration, 2)

Control rod position, 3)

Reactor Coolant System average temperature, 4)

Fuel burnup based on gross thermal energy generation, 5)

Xenon concentration, and 6)

Samarium concentration.

4.1.1.1.2 The overall core reactivity balance shall be compared to predicted values to demonstrate agreement within i 1% Ak/k at least once per 31 Effective Full Power Days (EFPD).

This comparison shall consider at least those factors stated in Specification 4.1.1.1.le...above.

The predicted reactivity values l

shall be adjusted (normalized) to correspond to the actual core conditions prior to exceeding a fuel burnup of 60 EFPD after each fuel loading.

4.1.1.1.3 (Unit 2 only) At least once per 18 months, the Reactor Makeup Water l

pumps sh'all be demonstrated OPERABLE by verifying a total combined flow rate of less than or equal to 240 gpm and a flow rate of less than or equal to 120 gpm for each pump.

4.1.1.1.4 (Unit 2 only) At least once per 31 days, while in MODE 4, one l

l Reactor Makeup Water pump shall be demonstrated inoperable by verifying that the motor circuit breaker is secured in the open position.

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1 CATAWBA - UNITS 1&2 3/4 1-2 Amendment No.17 (Unit 1)

Amendment No. 7 (Unit 2)

REACTIVITY CONTROL SYSTEMS SHUTOOWN MARGIN - T

< 200 F ava LIMITING CONDITION FOR OPERATION 3.1.1.2 The SHUTDOWN MARGIN shall be greater than or equal to 1% Ak/k.

APPLICABILITY: -MODE 5.

ACTION:

With the SHUTDOWN MARGIN less than 1% Ak/k, immediately initiate and continue boration at greater than or equal to 30 gpm of a solution containing greater than or equal to 7000 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored.

SURVEILLANCE REQUIREMENTS 4.1.1.2.1 The SHUTDOWN MARGIN shall be determined to be greater than or equal to 1% Ak/k:

a.

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after detection of an inoperable control rod (s) and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter while the rod (s) is inoperable.

If the inoperable control rod is immovable or untrippable, the SHUTDOWN MARGIN shall be verified acceptable with an increased allowance for the withdrawn worth of the immovable or untrippable control rod (s); and b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by consideration of the following factors:

1)

Reactor Coolant System boron concentration, 2)

Control rod 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 (Unit 2 only) At least once per 18 months, each Reactor Makeup Water l

pump shall be demonstrated OPERABLE by verifying a flow rate of less than or equal to 120 gpm.

At least once per 31 days, one Reactor Makeup Water pump shall be demonstrated inoperable by verifying that the motor circuit breaker is secured in the open position.

CATAWBA - UNITS 1&2 3/4 1-3 Amendment No.17 (Unit 1)

Amendment No. 7(Unit 2)

REACTIVITY CONTROL SYSTEMS MODERATOR TEMPERATURE COEFFICIENT p

LIMITING CONDITION FOR OPERATION 3.1.1.3 The moderator temperature coefficient (MTC) shall be:

a.

Less positive than 0 ak/k/ F for all the rods withdrawn, beginning of cycle life (BOL), hot zero THERMAL POWER condition; and b.

Less negative than -3.7 x 10 4 Ak/k/ F for all the rods withdrawn, end of cycle life (E0L), RATED THERMAL POWER condition.

APPLICABILITY:

Specification 3.1.1.3a. - MODES 1 and 2* only#.

Specification 3.1.1.3b. - MODES 1, 2, and 3 only#.

ACTION:

a.

With the MTC more positive than the limit of Specification 3.1.1.3a. above, operation in MODES 1 and 2 may proceed provided:

1.

Control rod withdrawal limits are established and maintained sufficient to restore the MTC to less positive than 0 ak/k/ F within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

These withdrawal limits shall~be in addition to the insertion limits of Specification 3.1.3.6; 2.

The control rods are maintained within the withdrawal limits established above until a subsequent calculation verifies that the MTC has been restored to within its limit for the all rods withdrawn condition; and 3.

A Special Report is prepared and submitted to the Commission pursuant to Specification 6.9.2 within 10 days, describing the value of the measured MTC, the interim control rod withdrawal limits, and the predicted average core burnup necessary for restoring the positive MTC to within its limit for the all rods withdrawn condition.

b.

With the MTC more negative than the limit of Specification 3.1.1.3b.

above, be in HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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With Keff greater than or equal to 1.

See Special Test Exceptions Specification 3.10.3.

A CATAWBA - UNITS 1 & 2 3/4 1-4

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3/4.3 INSTRUMENTATION i

3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION v>

LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the Reactor Trip System instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE with RESPONSE TIMES as shown in Table 3.3-2.

APPLICABILITY: As shown in Table 3.3-1.

ACTION:

As shown in Table 3.3-1.

SURVEILLANCE REQUIREMENTS

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4.3.1.1 Each Reactor Trip System instrumentation channel and interlock and the automatic trip logic shall be demonstrated OPERABLE by the performance of the Reactor Trip System Instrumentation Surveillance Requirements specified in Table 4.3-1.

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4.3.1.2 The REACTOR TRIP SYSTEM RESPONSE TIME of each Reactor trip. function shall be demonstrated to be within its limit at least once per 18 months.

Each test shall include at least one train such that both trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function as shown in the

" Total No. of Channels" column of Table 3.3-1.

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0 REACTOR TRIP SYSTEM INSTRUMENTATION Ey MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION c-5 d

1.

Manual Reactor Trip 2

1 2

1, 2 -

1 2

3*,

4*, 5*

10

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2.

Power Range, Neutron Flux m

a.

High Setpoint 4

2 3

1, 2 2#

b.

Low Setpoint 4

2 3

1###, 2 2#

3.

Power Range, Neutron Flux 4

2 3

1, 2 2#

l High Positive Rate 4.

Power Range, Neutron Flux, 4

2 3

1, 2 2#

R High Negative Rate 5.

Intermediate Range, Neutron Flux 2

1 2

1###, 2 3

6.

Source Range, Neutron Flux a.

Startup 2

1 2

2##

4-b.^ Shutdown (Unit 1) 2 1

2 3*, 4*, 5*

10 (Unit 2) 2 1

2 3, 4, 5 5

7.

Overtemperature AT l

Four Loop Operation 4

2 3

1, 2 6#

8.

Overpower AT kg Four Loop Operation 4

2 3

1, 2 6#

3 EE

,5 g 9.

Pressurizer Pressure-Low 4

2 3

1 6#**

55 FF Lb 22 hh SC

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1 TABLE 4.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS c

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TRIP ANALOG ACTUATING MODES FOR c:

CHANNEL DEVICE WHICH 25 CHANNEL CHANNEL OPERATIONAL UPERATIONAL ACTUATION SURVEILLANCE DI FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED-18.

Reactor Trip System Interlocks (Continued) no e.

Power Range Neutron i

Flux, P-10 N.A.

R(4)

M(8)

N' A.

N.A.

1 f.

Power Range Neutron

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Flux, Not P-10 N.A.

R(4)

M(8)

N.A.

N. A.

1, 2 i

g.

Turbine Impulse Chamber

}{

Pressure, P-13 N.A.

R M(8)

N.A.

1.

T 19.

Reactor Trip Breaker N.A.

N.A.

M(7, 11)

N.A.

1, 2, 3*, 4*, 5*

l L:

i 20.

Automatic Trip and Interlock N.A.

N.A.

M(7) 1, 2, 3*, 4*, 5*

i Logic 4

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TABLE 4.3-1 (Continued)

TABLE NOTATIONS Only if the Reactor Trip System breakers happen to be closed and the Control Rod Drive System is capable of rod withdrawal.

Above P-9 (Reactor Trip on Turbine Trip Interlock) Setpoint.

Below P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.

1. 1. Below P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

(1) If not performed in previous 7 days.

(2) Comparison of calorimetric to excore power indication above 15% of RATED THERMAL POWER.

Adjust excore channel gains consistent with calorimetric power if absolute difference is greater than 2%.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(3) Single point comparison of incore to excore axial flux difference above 15% of RATED THERMAL POWER.

Recalibrate if the absolute difference is greater ~than or equal to 3%.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(4) Neutron detectors may be excluded from CHANNEL CALIBRATION.

(5) Detector plateau curves shall be obtained, evaluated and compared to manufacturer's data.

For the Intermediate Range and Power Range Neutron Flux channels the provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(6) Incere - Excore Calibration, above 75% of RATED THERMAL POWER. The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(7) Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.

(8) With power greater than or equal to the interlock setpoint the required ANALOG CHANNEL OPERATIONAL TEST shall consist of verifying that the interlock is in the required state by observing the permissive status light.

(9) Mor.thly surveillance in MODES 3*, 4*, and 5* shall also include verifi-cation that permissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive status light.

For Unit 2 only, monthly surveillance shall include verification of the l

Bcron Dilution Alarm Setpoint of less than or equal to one-half decade (square root of 10) above background.

(10) Setpoint verification is not applicable.

(11) At least once per 18 months and following maintenance or atfjustment of the Reactor trip breakers, the TRIP ACTUATING DEVICE OPERATIONAL TEST shall include independent verification of the Undervoltage and Shunt trips.

(12) CHANNEL CALIBRATION shall include the RTD bypass loops flow rate.

(13) For Unit 1, CHANNEL CALIBRATION shall ensure that the filter time constant associated with Steam Generator Water Level Low-Low is adjusted to a value less than or equal to 1.5 seconds.

CATAWBA - UNITS 1 & 2 3/4 3-12 Amendment No. 17 (Unit 1)

Amendment No.

7 (Unit 2)

INSTRUMENTATION 4

3/4.3.3.12 BORON DILUTION MITIGATION SYSTEM LIMITING CONDITION FOR OPERATION 3.3.3.12 As a minimum, two trains of the Boron Dilution Mitigation System shall be OPERABLE and operating with Shutdown Margin Alarm ratios set at less than or equal to 4 times the steady-state count rate.

APPLICABILITY:

MODES 3, 4, AND 5 (UNIT 1 ONLY)

ACTION:

(a) With one. train of the Boron Dilution Mitigation System inoperable or not operating, restore the inoperable train to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , or (1) suspend all operations involving positive reactivity changes and verify that valve NV-230 is closed and secured within the next hour, or

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(2) verify two Source Range Neutron Flux Monitors are OPERABLE with Alarm Setpoints less than or equal to one-half decade above the steady-state count rate and verify that the combined flowrate from both Reactor Makeup Water Pumps is less than or equal to 200 gpm (Mode 3) or 80 gpm (Mode 4 or 5) within the next hour.

(b) With both trains of the Boron Dilution Mitigation System inoperable or not operating, restore the inoperable trains to OPERABLE status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , or (1) suspend all operations involving positive reactivity changes and verify that valve NV-230 is closed and secured within the next hour, or (2) verify two Source Range Neutron Flux Monitors are OPERABLE with Alarm Setpoints less than or equal to one-half decade above the steady-state count rate and verify that the combined flow rate from both Reactor Makeup Water Pumps is less than or equal to 200 gpm (Mode 3) or 80 gpm (Mode 4 or 5) within the next hour.

(c) The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.12.1 Each train of the Boron Dilution Mitigation System shall be demon-strated OPERABLE by performance of:

(a) A CHANNEL CHECK at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , CATAWBA - UNITS 1 & 2 3/4 3-92a Amendment No.17(Unit 1)

Amendment No. 7(Unit 2)

INSTRUMENTATION SURVEILLANCE REQUIREMENTS (Continued)

(b) An ANALOG CHANNEL OPERATIONAL TEST prior to startup if not performed in previous 7 days, and (c) An ANALOG CHANNEL OPERATIONAL TEST at least once per 31 days.

(d) At least once per 18 months the BDMS shall be demonstrated OPERABLE by:

(1) Verifying that each automatic valve actuated by the BDMS moves to its correct position upon receipt of a trip signal, and (2) Verifying each reactor makeup water pump stops, as designed, upon receipt of a trip signal.

4.3.3.12.2.If using the Source Range Neutron Flux Monitors to meet the require-ments of Technical Specification 3.3.3.12, (a) The monthly surveillance requirementc.of Table 4.3-1 for the Source Range Neutron Flux Monitors shall include verification that the Alarm Setpoint is less than or equal to one-half decade (square root of 10) above the steady-state count rate.

(b) The combined flow rate from both Reactor Makeup Water Pumps shall be verified as less than or equal to 200 gpm (Mode 3) or 80 gpm (Mode 4 or 5) at least once per 31 days.

e CATAWBA - UNITS 1 & 2 3/4 3-92b Amendment No.17 (Unit 1)

Amendment No. 7(Unit 2)

3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION LIMITING CONDITION FOR OPERATION 3.9.1 The boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained uniform and sufficient to ensure that the more restrictive of the following reactivity conditions is met either:

a.

AK f 0.95 or less, or eff b.

A boron concentration of greater than or equal to 2000 ppm.

APPLICABILITY:

MODE 6.*

ACTION:

With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity

~~

changes and initiate and continue boration at greater than or equal to 30 gpm of a solution containing greater than or equal to 7000 ppm boron or its equivalentuntilK[(oredtogreaterthanorequalto2000 ppm,whicheveris is reduced to less than or equal to 0.95 or the boron concentrationisr$

the more restrictive.

SURVEILLANCE REQUIREMENTS 4.9.1.1 The more restrictive of the above two reactivity conditions shall be determined prior to:

a.

Removing or unbolting the reactor vessel head, and b.

Withdrawal of any full-length control rod in excess of 3 feet from its fully inserted position within the reactor vessel.

4.9.1.2 The boron concentration of the Reactor Coolant System ana the refueling canal shall be determined by chemical analysis at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

4.9.1.3 Valve NV-230 shall be verified closed and secured in position by l

mechanical stops at least once per 31 days.

The reactor shall be maintained in MODE 6 whenever fuel is in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.

CATAWBA - UNITS 1 & 2 3/4 9-1 Amendment Nol7 (Unit 1)

Amendment No. 7 (Unit 2)

REFUELING OPERATIONS 3/4.9.2 INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.9.2.1 As a minimum, two trains of the Boron Oilution Mitigation System shall be OPERABLE and operating with Shutdown Margin Alarm Ratios set at less than or equal to 4 times the steady-state count rate, each with continuous indication in the control room.

APPLICABILITY: MODE 6 (UNIT 1 ONLY)

ACTION:

(a) With one or both trains of the Boron Dilution Mitigation System inoperable or not operating, (1) immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes, or (2) verify that two Source Range Neutron Flux Monitors are OPERABLE

~~

and operating with Alarm Setpoints less than or equal to one-half decade (square root of 10) above the steady-state count rate, each with continuous visual indication in the control room and one with audible indication in the control room and one with audible indication in the containment and control room within the next hour.

(b) With both trains of the Boron Dilution Mitigation System inoperable or not operating and one of the Source Range Neutron Flux Monitors inoperable or not operating immediately suspend all operations involving core ALTERATIONS or positive reactivity changes.

(c) With both trains of the Boron Dilution Mitigation System inoperable or not operating and both of the Source Range Neutron Flux Monitors inoperable or not operating, determine the boron concentration of the Reactor Coolant System at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REQUIREMENT 4.9.2.1.1 Each train of the Boron Dilution Mitigation System shall be demon-strated OPERABLE by performance of:

(a) A CHANNEL CHECK at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , (b) An ANALOG CHANNEL OPERATIONAL TEST within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to the initial start of CORE ALTERATIONS and (c) An ANALOG CHANNEL OPERATIONAL TEST at least once per 31 days.

CATAWBA - UNITS 1 & 2 3/4 9-la Amendment No.17(Unit 1)

Amendment No. 7(Unit 2)

.. c o

REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS (CONTINUED)

(d) At least once per 18 months the BDMS shall be demonstrated OPERABLE by:

(1) Verifying that each automatic valve actuated by the BDMS moves to its correct position upon receipt of a trip signal, and j

(2) Verifying each reactor makeup water pump stops, as designed, upon receipt of a trip signal.

4.9.2.1.2 If using the Source Range Neutron Flux Monitors to meet the require-ments of Technical Specification 3.9.2, each Source Range Neutron Flux Monitor shall be demonstrated OPERABLE by performance of:

(a) A CHANNEL CHECK at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , (b) An ANALOG CHANNEL OPERATIONAL TEST within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to the initial start of CORE ALTERATIONS or within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after declaring the BORON DILUTION MITIGATION SYSTEM inoperable, and (c) An ANALOG CHANNEL OPERATIONAL TEST at lest once per 7 days.

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CATAWBA - UNITS 1 & 2 3/4 9-lb Amendment No.17(Unit 1) l Amendment No. 7(Unit 2)

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REFUELING OPERATIONS 3/4.9.2 INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.9.2.2 As a minimum, two Source Range Neutron Flux Monitors shall be OPERABLE l

and operating with Alarm Setpoints at 0.5 decade above steady-state count rate, each with continuous visual indication in the control room and one with audible indication in the containment and control room.

APPLICABILITY:

MODE 6 (UNIT 2 only)

ACTION:

With one of the above required monitors inoperable or not operating, a.

immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

.b.

With both of the above required monitors inoperable or not operating, determine the boron concentration of the Reactor Coolant System at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REQUIREMENTS 4.9.2.2 Each Source Range Neutron Flux Monitor shall be demonstrated OPERABLE l

by performance of:

a.

A CHANNEL CHECK at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , b.

An ANALOG CHANNEL OPERATIONAL TEST within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to the initial start of CORE ALTERATIONS, and An ANALOG CHANNEL OPERATIONAL TEST at least once per 7 days.

c.

d CATAWBA - UNITS 1 & 2 3/4 9-2 Amendment No.17(Unit 1)

Amendment No. 7(Unit 2)

4-INSTRUMENTATION BASES 3/4.3.3.12 BORON DILUTION MITIGATION SYSTEM The operability of the Boron Dilution Mitigation System ensures that pro-tection against a loss of shutdown' margin from a boron dilution event is pre-sent. This system uses two source range detectors to monitor the subcritical multiplication of the reactor core.

An alarm setpoint is continually calcu-lated as 4 times the lowest measured count rate, including compensation for background and the statistical variation in the count rate.

Once the alarm setpoint is exceeded, each train of the Boron Dilution Mitigation System will automatically shut off both Reactor Makeup Water Pumps, isolate flow to the charging pumps from the Volume Control Tank, and align the suction of the charging pumps to highly borated water from the RWST.

These actions automa-tically isolate the potential sources of diluted water and allow injection of highly borated water into the Reactor Coolant System.

In the event that the Boron Dilution Mitigation System is inoperable or not operating, the Source Range Neutron Flux Monitors may be used to provide protection against a loss of shutdown margin from a boron dilution event.

If the Source Range Neutron Flux Monitors are used to monitor the subcritical multiplication of the reactor core, the alarm setpoint must be calibrated and periodically checked to ensure that it is less than or equal to one-half decade above the steady-state count rate.

In addition, the flow from the Reactor Make-up Water Pumps must be verified as below specified limits.

These actions ensure that adequate time is available for the operator to recognize and terminate a dilution event prior to a loss of shutdown margin.

3/4.3.4 TURBINE OVERSPEED PROTECTION This specification is provided to ensure that the turbine overspeed protection instrumentation and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed.

Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety-related components, equipment, or structures.

CATAWBA - UNITS 1 & 2 B 3/4 3-7 Amendment No.17(Unit 1)

Amendment No. 7(Unit 2)

3/4.9 REFUELING OPERATIONS BASES 3/4.9.1 BORON CONCENTRATION The limitations on reactivity conditions during REFUELING ensure that:

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

These limitations are consistent with the initial conditions assumed for the boron dilution incident in the safety analyses. The value of 0.95 or less for K,77 includes a 1% Ak/k conservative allowance for uncertainties.

Similarly, the boron concentration value of 2000 ppm or greater includes a conservative uncertainty allowance of 50 ppm boron.

The locking closed of the required valves during refueling operation precludes the possibility of uncontrolled boron dilution of the filled portion of the Reactor Coolant System.

This action prevents flow to the Reactor Coolant System of unborated water by closing flow paths from sources of unborated water.

3/4.9.2 INSTRUMENTATION The OPERABILITY of the Source Range Neutron Flux Monitors and/or the Baron Dilution Mitigation System ensures that redundant monitoring capability is available to detect changes in the reactivity condition of the core.

3/4.9.3 DECAY TIME The minimum requirement for reactor subcriticality prior to movement of irradiated fuel assemblies in the reactor vessel ensures that sufficient time has elapsed to allow the radioactive decay of the short-lived fission products.

This decay time is consistent with the assumptions used in the safety analyses.

3/4.9.4 CONTAINMENT BUILDING PENETRATIONS The requirements on containment building penetration closure and OPERABILITY of the Reactor Building Containment Purge System ensure that a release of radioactive material within containment will be restricted from leakage to the environment or filtered through the HEPA filters and charcoal adsorbers prior to release to the atmosphere.

The OPERABILITY and closure restrictions are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressurization potential while in the REFUELING MODE.

Operation of the Reactor Building Containment Purge System and the resulting iodine removal capacity are consistent with the assumption of the safety analysis.

Operation of the system with the heaters operating to maintain low humidity using automatic control for at least 10 continuous hours in a 31-day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters.

ANSI N510-1980 will be used as a procedural guide 1

for surveillance testing.

l 1

CATAWBA - UNITS 1 & 2 8 3/4 9-1 Amendment NoJ7 (Unit 1)

Amendment No. 7 (Unit 2)

o,

REFUELING OPERATIONS BASES 3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity conditions during CORE ALTERATIONS.

3/4.9.6 MANIPULATOR CRANE The OPERABILITY requirements for the manipulator cranes ensure that:

(1) manipulator cranes will be used for movement of control rods and fuel-assemblies, (2) each crane has sufficient load capacity to lift a control rod or fuel assembly, and (3) the core internals and reactor 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 POOL BUILDING The restriction on movement of loads in excess of the nominal weight of a fuel and control rod assembly and associated handling tool 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 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 safety analyses.

3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION The requirement that at least one residual heat removal loop be in operation ensures that:

(1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor vessel below 140 F as required during the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the core to minimize the effect of a boron dilution incident and prevent boron stratification.

The requirement to have two residual heat removal loops OPERABLE when there is less than 23 feet of water above the reactor vessel flange ensures that a single fail _ure of the operating residual heat removal loop will not result in a complete loss of residual heat removal capability. With the reactor vessel head removed and at least 23 feet of water above the. reactor vessel flange, a large heat sink is available for core cooling.

Thus, in the Qvent of a failure of the operating residual heat removal loop, adequate time is provided to initiate emergency procedures to cool the core.

k CATAWBA - UNITS 1 & 2 B 3/4 9-2

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ML20215N176

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