ML20065L466

Amends 80 & 74 to Licenses NPF-35 & NPF-52,respectively, Revising Tech Specs to Eliminate Typos,Provide Addl Clarification & Improve Consistency

ML20065L466
Person / Time
Site:	Catawba
Issue date:	11/29/1990
From:	Matthews D Office of Nuclear Reactor Regulation
To:
Shared Package
ML20065L467	List: ML20065L466 ML20065L469
References
NUDOCS 9012070070
Download: ML20065L466 (29)

Text

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UNITED STATES

[ ',,.j#<.(i NUCLEAR REGULATORY COMMISSION s

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WAbalNG TON. D. C. 20555 "s'4..... '

p DUKE POWER COMPAlh NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPEPATIVE, INC.

DOCKET NO. 50-413 CATAWBA tiUCLEAR STATION, UNIT 1 AMEN 0 MENT TO FACillTY OPERATING LICENSE Amendment No. 80 License No. hPF-35 1.

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

A.

The application for amendment to the Catawba Nuclear Station, l' nit 1 (the facility) Facility Operating License No. NPF-35 filed by the Duke Power Company acting for itself, North Carolina Electric Membership Corporation and Saluda River Electric Cooperative, Inc.

(licensecs) dated October 28, 1987, and supplemented October 30 and November 10,1989, July 13 and September 25, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amendtd (the Act), and the Connission's rules and regulations as set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (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 Connission's regulations set forth in 10 CFR Chapter I; 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.

lne issuance of this amendment is in accordance with 10 CFR Part 51 l

of the Commission's regulations and all applicable requirements have been satisfied.

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2.

Accordingly, the license is hereby amended by page char.ges to the Technical Specifications as indicated in the attachment to this license amendment, i

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

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.

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

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION c

1MeV) AS A FUNCTION OF FULL POWER SERVICE LIFE..................................

B 3/4 4-11 3/4.4.10 STRUCTURAL INTEGRITY..........................

B 3/4 4-16 3/4.4.11 REACTOR COOLANT SYSTEM VENTS.......................

B 3/4 4-17 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS..............................................

B 3/4 5-1 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS...............................

B 3/4 5-2 l

3/4.5.4 REFUELING WATER STORAGE TANK..............................

B 3/4 5-2 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT.......................................

B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS.................

B 3/4 6-4 3/4.6.3 CONTAINMENT ISOLATION VALVES...........................

B 3/4 6-4 3/4.6.4 COMBUSTIBLE GAS CONTR0L...................................

B 3/4 6-4 3/4.6.5 ICE CONDENSER............................................

B 3/4 6-5 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE...............

B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION...........

B 3/4 7-2a 1

3/4.7.3 COMPONENT COOLING WATER SYSTEM............................

B 3/4 7-3 3/4.7.4 NUCLEAR SERVICE WATER SYSTEM..............................

B 3/4 7-3 3/4.7.5 STANDBY NUCLEAR SERVICE WATER P0ND........................

B 3/4 7-3a 3/4.7.6 CONTROL ROOM AREA VENTI LATION SYSTEM......................

B 3/4 7-3a 3/4.7.7 AUXILIARY BUILDING FILTERED EXHAUST SYSTEM................

B 3/4 7-4 3/4.7.8 SNUBBERS.

B 3/4 7-4 3/4.7.9 SEALED SOURCE CONTAMINATION...............................

B 3/4 7-6 3/4.7.10 FIRE SUPPRESSION SYSTEMS..................................

B 3/4 7-6 3/4.7.11 FIRE BARRIER PENETRATIONS.................................

B 3/4 7-7 3/4.7.12 GROUNDWATER LEVEL.........................................

B 3/4 7-7 3/4.7.13 STANDBY SHUTDOWN SYSTEM...................................

B 3/4 7-8 CATAWBA - UNITS 1 & 2 XIV Amendment No. 80 (Unit 1)

Amendment No. 74 (Unit 2) o

i TABLE 3.3-3 (Continued) nM E

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM IfiSTRUMENTATION SE C5 MINIMUM d

TOTAL f40.

CHANNELS CHANNELS APPLICABLE l

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION I

o.

m 4.

Steam Line Isolation (Continued) i e

e.

Steam Line Pressure -

3/ steam line 2/ steam line 2/ steam line 34 15 j

Negative Rate-High in any steam line i

5.

Feedwater Isolation i

w a.

Automatic Actuation 2

1 2

1, 2 27 I

2 Logic and Actuation Relays I

w Ei' b.

Steam Generator 4/stm. gen.

2/stm. gen.

3/stm. gen.

1, 2 19 Water Level-in any oper-in each oper-(

High-High (P-14)

.ating stm.

ating stm.

gen.

gen.

c.

T

-Low (P-4 avg EE Interlock) 4 2

3 1, 2 19 mm El d.

Doghouse Water i

@8 Level-High 2/ doghouse 1/ doghouse 2/ doghouse 1, 2 27 l

55 in any doghouse EE e.

Safety Injection See Item 1. above for all Safety injection initiating functions and requirements.

%E 6.

Turbine Trip i

G i

oo22 a.

Manual Initiation 1

1 1

1,2 25 it-'

b.

Automatic Actuation Logic and Actuation Relays 2

1 2

1,2 27

TABLE 3.3-3 (Continued) n3p ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION E

MINIMUM 3

TOTAL NO.

CHANNELS CHANNELS APPLILABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION g

1 e-l 6.

Turbine Trip (Continued) m c.

Steam Generator Water Level-High-High (P-14) 4/stm. gen.

2/stm. gen.

3/stm. gen.

1,2 19 in any in each operating sim. operating stm.

gen.

gen.

d.

Trip of All Main

{

Feedwater Pumps 2/ pump 1/ pump 1/ pump 1,2#

25 e.

Reactor Trip (P-4) 2 1

2 1,2,3 22 I

g f.

Safety Injection See Item 1. above for all Safety Injection initiating functions and requirements.

7.

Containment Pressure Control System a.

Start Permissive 4/ train 2/ train 3/ train 1, 2, 3, 4 19

((

soEE b.

Termination 4/ train 2/ train 3/ train 1, 2, 3, 4 19 8.

Auxiliary Feedwater EE a.

Manual Initiation 1/ train 1/ train 1/ train 1, 2, 3 26 Q

no b.

Automatic Actuation Logic 2

1 2

1,2,3 21

^^

((

and Actuation Relays eo f

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS 4.7.12 The groundwater level shall be determined at the following frequencies by monitoring the water level and by verifying the absence of alarm in the six groundwater monitor wells as shown in FSAR Figure 2.4.13-14 installed around the perimeter of the Reactor and Auxiliary Buildings:

l a.

At least once per 7 days when the groundwater leeel is at or below the top of the adjacent floor slab, and b.

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the groundwater level is above the top of the adjacent floor slab.

P l

l CATAWBA - UNITS 1 & 2 3/4 7-39 Amendment No. 80 (Unit 1)

Amendment No. 74 (Unit 2)

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PLANT SYSTEMS 3/4.7.13 STANDBY SHUTDOWN SYSTEM LIMITING CONDITION FOR OPERATION 3.7.13 The Standby Shutdown System (SSS) shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3.

ACTION:

(Units 1 and 2)

With the Standby Shutdown System inoperable, restore the iroperable a.

equipment to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, b.

With the total leakage from UNIDENTIFIED LEAKAGE, IDENTIFIED LEAKAGE and reactor coolant pump seal leakage greater than 26 gpm, declare the Standby Makeup Puns inoperable and take ACTION a,, abcVe, The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

c.

SURVEILLANCE REQUIREMENTS 4.7.13.1 The Standby Shutdown System diesel generator shall be demonstrated OPERABLE:

a.

At least once per 31 days by verifying:

1) _ The fuel level in the fuel storage tank is greater than or equal to'67 inches, and 2)

The' diesel starts from ambient conditions and operates for at least 30 minutes-at greater than or equal to 700 kW.

b.

-At least once per 92 days by verifying that a sample of diesel fuel

.from the fuel storage tank, obtained in accordance with ASTM-D270-1975,

_is _within the acceptable limits specified in Table 1 of ASTM-D975-1977 when checked for viscosity and water and sediment; and c.

At least once per 18 months, during shutdown, by subjecting the diesel _

to an inspection in accordance with procedures prepared in conjunction with its manufacturer's. recommendations for the class of service.

l l

4.7.13.2 The Standby Shutdown System diesel starting M-volt battery bank and L

charger shall be demonstrated OPERABLE:

At least _once per'7 days by verifying that:

a.

1)

The electrolyte level of each battery is at,ove the plates; and 2)

The overall battery voltage is greater than or equal to 24 volts.

L CATAWBA - UNITS 1 & 2 3/4 7-40

s s

ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continue 41

11) Verifying that the fuel transfer valve transfers fuel from each fuel storage tank to the day tank of each diesel via the in-stalled cross-connection lines;

12) Verifying that the automatic load sequence timer is OPERABLE with the interval between each load block within the tolerances given in Table 4.8-2;

13) Verifying that the voltage and diesel speed tolerances for the accelerated sequencer permissives are 92.5 : 1% and 98 + 1%,

respectively, with a time delay of 2 : 0.2 s; l

14) Verifying that the following diesel generator lockout features prevent diesel generator starting only when required:

a)

Turning gear engaged, or b)

Maintenance mode; and

15) Operating at greater than or equal to 5600 KW but less than or equal to 5750 KW for one hour or until operating temperature has stabilized. Within 5 minutes af ter completing this test, perform Specification 4.8.1.1.2.6)b).

9 h.

At least once t ar 10 years or after any modifications which could affect diesel generator interdependence by starting both diesel generators simultaneously, during shutdown, and verifying that both diesel generators accelerate to at least 441 rpm in less than or equal to 11 seconds; and i.

At least once per 10 years by:

1)

Draining each fuel oil storage tank, removing the accumulated sediment and cleaning tne tank using a sodium hypochlorite solution or its equivalent, and 2)

Performing a pressure test of those portions of the diesel fuel oil system designed to Section III, subsection ND of the ASME Code at a test pressure equal to 110% of the system design pressure.

3)

Ferforming tank wall thickness measurements. The resulting data shall be evaluated and any abnormal degradation will tue justified or corrected.

Any abnormal degradation will be documented in a report to the Commission.

4.8.1.1.3 Reports - All diesel generator failures, valid or non-valid, shall be reported in a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days.

Reports of diesel generator failures shall include the informa-tion recommended in Regulatory Position C.3 b of Regulatory Guide 1.108, Revi-sion 1, August 1977.

If the number of failures in the last 100 valid tests of any diesel generator is greater than or equal to 7, the report shall be supplemented to include the additional information recommended in Regulatory Position C.3.b of Regulatory Guide 1.108, Revision 1, August 1977.

1 CATAWBA - UNITS 1 & 2 3/4 8-7 Amendment No. 80 Unit 1 l

Amendment No. 74 Unit 2

- -. - -._~ - - - -

- j 5.0 DESIGN FEATURES j

5.1 SITE EXCLUSION AREA 5.1.1 The Exclusion Area shall be as shown in Figure 5.1-1.

LOW POPULATION ZONE 5.1.2 The Low Population Zone shall be as shown in Figure 5.1-2.

MAPS DEFINING U'NRESTRICTED AREAS AND SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS _

5.1.3 Information regarding radioactive gaseous and liquid effluents, which will-allow identification of structures and release points as well as defini-tion of UNRESTRICTED AREAS within the SITE BOUNDARY that are accessible to MEMBERS OF_THE PUBLIC, shall be as shown in Figures 5.1-3 and 5.1-4 The definition of UNRESTRICTED AREA used in implementing these Technical Specifications has been expanded over that in 10 CFR 20.3(a)(17).

The UNRESTRICTED AREA boundary may coincide with the Exclusion (fenced) Area boundary, as defined in 10 CFR 100.3(a), but the UNRESTRICTED AREA does not include areas over water bodies.

The concept of UNRESTRICTED AREAS, established at or beyond.the SITE BOUNDARY, is utilized in the Limiting Conditions,for Operation to keep levels of radioactive materials in liquid and gaseous effluents as low as is _ reasonably achievable, pursuant to 10 CFR 50.36a.

5.2 CONTAINMENT CONFIGURATION 5.2.1 The containment structure is comprised of a' steel containment vessel surrounded by a concrete containment _having the following design features:

a.

QntainmentVessel 1)-

Nominal-inside diameter = 115 feet.

2)

Nominal inside-height = 171 feet.

3).Ncminal thickness of vessel walls = 0.75 inch.'-

4)

Nominal-thickness of vessel dome =-0,6875 inch.

5)

Nominal thickness of vessel _ bottom = 0.25 inch.

6)

Net free volume = 1.2 x 106 cubic feet.

i b.

Reactor Building 1)

Nominal: Annular space = 6 feet.

2) -Annulus nominal volume = 484,090 cubic' feet.

3)

Nominal outside height (top of foundation base to top of dome) = 177 feet.

4).

Nominal inside diameter = 127 feet.

5)

Minimum cylinder wall thickness = 3 feet.

6).

Minimum dome thickness = 2.25 feet.

7)

Dome inside radius = 87 feet.

CATAWBA - UNITS 1 & 2 5-1

.a

SITE BOUNDARY PERIMETER FENCE g g **

+-

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l IV

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t 4

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NUCLEAR SERVICE b

1_

WATER POND[

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2500 FT. R.

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EXCLUSION

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BOUNDARY

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, INTAKE STRUCTURE

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t

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x g ;;;7;; 1;in.w wa>>''':

Y REACTOR 3 y

STATION VENTS ln TURBINE BLDGS.f BLDGS.

(GASEOUS RELEASE

[M,/

f' POINTS EL. 718,75)

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SWITCH I

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YARD COO' LING

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NTOWER

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N ' ARD

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OAD BLOG, o i _

.y ACCESS R g

METEOR GICAL 4

TOWER TRAININ CENTER ]G h'

DISCHARGE U

4

) \\.+!

STRUCTURE l

(LlQUID RELEAS l

POINT) x l.

i

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.f FIGURE 5.1-1 EXCLUSION AREA i

CATAWBA - UNITS 1 AND 2 5-2 Amendment No. 80 (Unit 1)

Amendment No. 74 -(Unit 2)

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FIGURE 5,1-2 LOW POPULATION ZONE CATAWBA - UNITS 1 & 2 5-3 4

SITE BOUNDARY PERIMETER FENCE g y

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NSW c'

DAM

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k-f

%y

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NUCLEAR SERVICE J-WATER POND J

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2500 FT. R.

EXCLUSION

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gf INTAKE STRUCTURE f

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ijplw,,,,',',',',' i i i > wl-; ;

; i 14+H4M V

< > ' ' ; i ; ; n. _

REACTOR STATION VENTS jj ABLDGS.

TURBINE BLDGS j

u J[/p (GASEOUS RELEASE POINTS EL. 718.75)

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SWITCH F-N*N x

YARD COOLING r

NTOWER AUX.

ARD

g ACCESS ROAD BLOG.

l_;

N"*N Q

TRAININ CENTER y

DISCHARGE 1

STRUCTURE (LIQUlO RELEAS POINT)

• CHEMICAL t

TREATMEN

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FIGURE 5.1-3 UNRESTRICTED AREA AND SITE BOUNDARY FOR RADIOACTIVE LIQUID EFFLUENTS-CATAWBA - UNITS 1 AND 2 5-4 Amendment No. 80 (Unit 1)

Amendment No. 74 (Unit 2).

/

SITE BOUNDARY v

PERIMETER FENCE g j^

g' M

,k j

j' r

/

NUCLEAR SERVICE WP

+/*

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WATER POND i

s N

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2500 FT. R.

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EXCLUSION

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< INTAKE STRUCTURE f'Vf' '+

,,,h, m h in>

i;;;;t+ l l t i t+1 l I l l l l I I IM

+N REACTOR /

STATION VENTS TURBINE BLDGS.t BLDGS.

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(GASEOUS RELEASE p

f POINTS EL. 718.75)

SWITCH P-

\\*\\x

~

• , YARD COOLING J

x TOWER j

AUX.

g ARD x

1 L.

.j ACCESS ROAD BLDG, j

7 s

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DISCHARGE

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STRUCTURE (LIQUID RELEAS POINT) j

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FIGURE 5.1-4 UNRESTRICTED AREA AND SITE BOUNDARY FOR RADIOACTIVE GASEOUS EFFLUENTS CATAWBA - UNITS 1 AND 2 5-5 Amendment No. 80 (Unit 1) l Amendment No. 74 (Unit 2)

.. ~.

h 3

ADMINISTRATIVE CONTROLS RESPONSIBILITIES'(continued) d.

Surveillance of selected C. ant operations ano..=intenance activities to provide indep'.ndent.erification* that they are,nerformed correctly and that human rcror, are reduced to as low as practuable, e.

Investigation rf selected unusual events and other occur.'ences as assigned by St stion Management or the Manager of Nuclear _ Mfety Assurance.

AUTHORITY 6.2.3.4 The CSRG shall report _to and advise the Manager of Nucleai Safety Assurance, on those areas of responsibility specified in-Section 6.2.3.

RECORDS 6.2,3.5 Records of activities performed by the CSRG shall be prepared and maintained.for the life of the station.

Summary reports of activities performed by the CSRG shall be forwarded each calendar month to the Manager of Nuclear Safety Assurance.

6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall serve in an advisory capacity to the Shift Supervisor.

6.3' UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifi-cations of ANSI N18.1-1971 for comparable positions, except for the Radiation Protection Manager, who shall meet or exceed the qualifications of Regulatory Guide 1.8,-September 1975.

The licensed Operators and Senior Operators shall also meet or exceed the minimum qualifications of the supplemental require-

.ments specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC t

letter to all licensees.**

6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Manager, Station Training Services and l

shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix A of 10 CFR Part 55-and th6 supplemental requirements specified in Sections A and C of_ Enclosure 1_of the March 28, 1980 NRC letter to all licensees, and_shall include familiarization with relevant industry operational experience.

l-

.i

• Not responsible for sign-off function.

• = *Except that the experience and other considerations described in Duke Power Company's letters dated August 28, 1985, and July 8,1986, are acceptable for -

the six and two applicants for SR0 licenses identified therein, respectively.

CATAWBA - UNITS 1 & 2 6-6a Amendment No. 80 (Unit 1)

Amendment No. 74 (Unit 2)

1 s

ADMINISTRATIVE CONTROLS

-6.5 REVIEW AND AUDIT 6.5.1 TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.1.1 Each procedure and program required by Specification 6.8 and other procedures which affeet nuclear safety, and changes thereto, shall be prepared by a qualified individual / organization.

Each such procedure, and changes thereto, shall be reviewed by an individual / group other than the individual /

group which prepared the procedure, or changes thereto, but who may be from the same organization as the individual / group which prepared the procedure, or changes thereto.

6.5.1.2 Proposed changes to the Appendix A Technical Specifications shall be prepared by a qualified individual / organization.

The preparation of each proposed Technical Specification change shall be reviewed by an individual /

group other than the individual / group which prepared the proposed change, but who may be from the same organization as the individual / group which prepared the proposed change.

Proposed changes to the Technical Specifications shall be approved by the Station Manager.

6.5.1.3 Proposed modifications to unit nuclear safety-related structures, systems, and components shall be-designed by a qualified individual / organization.

Each such modification shall be reviewed by an individual / group other than the individual / group which designed the modification, but who may be from the same organization as the individual / group which designed the modification.

Proposed

. modification i.o nuclear safety-related structures, systems, and components shall be approved prior to implementation by the Station Manager; or by-the Operating Superintendent, the Technical Services Superintendent, the Maintenance Superintendent, or the Superintendent of Integrated Scheduling, as previously designated by the Station Manager.

6.5.1.4 Individuals responsible for reviews performed in accordance with Specifications.6.5.1.1, 6.5.1.2, and 6.5.1.3 shall be members of the station supervisory staff, previously designated by the Station Manager to perform such reviews.

Review of environmental radiological analysis procedures shall be performed by the Corporate System Health Physicist or his designee.

Each such review shall include a determination of whether or not additional, cross-disciplinary, review is necessary.

If deemed necessary, such review shall be performed by the appropriate designated station review personnel.

6.5.1.5 Proposed tests and experiments which affect station nuclear safety and are not addressed in the FSAR or Technical Specifications shall be reviewed by the' Station Manager; or by the Operating Superintendent, the Technical Services SuperinteMant, the Maintenance Superintendent, or the Superintendent of. Integrated Scheduling, as previously designated by the Station Manager.

CATAWBA - UNITS 1 & 2 6-7 Amendaert No. 80 (Unit 1)

Agendment No. 74 (Unit 2)

i

o-j

_a_qMINISTRATIVECONTROLS-TECHNICAL REVIEW AND CONTROL ACTIVITIES (Continued) 6.5.1.6 All REPORTABLE EVENTS and all violations of Technical Specifications shall be investigated and a report prepared which evaluates the occurrence and which provides recommendations to prevent recurrence.

Such reports shall be approved by the Station Manager and transmitted to the Vice President, Nuclear Production, and to the Nuclear Safety Review' Board.

l 6.5.1.7 The Station Manager shall assure the performance of special reviews and investigations, and the preparation and submittal of reports thereon, as requested by the Vice President, Nuclear Production.

6.5.1.8-The station security program, and-implementing procedures shall be

-l reviewed at least once per 12 months.

Recommended changes shall be approved s

by the Superintendent of Station Services and transmitted to the Vice President, Nuclear Production, and to the Nuclear Safety Review Board.

l 6.5.1.9 The station emergency plan, and implementing procedures, shall be reviewed at least once per 12 months.

Recommended changes shall be approved by the Station Manager and transmitted to the Vice President, Nuclear Production, and to the Nuclear Safety Review Board.

l 6.5.1.10 The Station Manager shall assure the performance of a review by a qualified individual / organization of every unplanned onsite release of radio-active material to the environs including the preparation and forwarding of reports covering evaluation, recommendations, and disposition of the corrective ACTION to prevent recurrence to the Vice President, Nuclear Production and to the Nuclear Safety Review Board.

6.5.1.11 The Station Manager shall assure the performance of a review by a qualifed individual / organization of changes--to the PROCESS CONTROL PROGRAM 0FFSITE DOSE CALCULATION MANUAL, and Radwaste Treatment Systems.

6.5.1.12 Reports documenting each of the activities performed under Specifications 6.5.1.1 through 6.5.1.11 shall be maintained.

Copies shall be provided to the Vice President, Nuclear Production, and the Nuclear Safety Review Board, 6.5.2 NUCLEAR SAFETY REVIEW BOARD (NSRB)

FUNCTION 6.5.'2.1 The NSRB shall-function to provide independent review and audit of designated activities in the areas of:

a.

Nuclear power plant operations, b.

Nuclear engineering, c.

Chemistry and radiochemistry, l

l l

CATAWBA - UNITS 1 & 2 6-8 Amendment No, 80 (Unit 1)

Amendment No. 74 (Unit 2)

s s

ADMINISTRATIVE CONTROLS AUDITS (Continued) c.

The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems, or method of operation that affect nuclear safety at least once per 6 months; d.

The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix B,10 CFR Part 50, at least once per 24 months;

\\

The Emergency Plan and implementing procedures at least once per e.

12 months; f.

The Security Plan and implementing procedures at least once per 12 months; g.

The Facility Fire Protection programmatic controls including the implementing procedures at least once per 24 months by qualified licensee QA personnel; h.

The fire protection equipment and program implementation at least once per 12 months utilizing either a qualified offsite licensee fire protection engineer or an outside independent fire protection consultant.

An outside independent fire protection consultant shall be used at least every third year; i.

The Radiological Environmental Monitoring Program and the results thereof at least once per 12 months; j.

The 0FFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months; k.

The PROCESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioactive wastes at least once per 24 months; 1.

The performance of activities required by the Quality Assurance Program for effluent and environmental monitoring at least once per 12 months; and m.

Any other area of unit operation considered appropriate by the NSRB or the Vice President, Nuclear Production.

RECORDS 6.5.2.10 Records of NSRB activities shall be prepared, approved, and distributed as indicated below:

a.

Minutes of each NSRB meeting shall be prepared, approved, and forwarded to the Vice President, Nuclear Production, and to the Executive Vice President, Power Group within 14 days l

following each meeting; CATAWBA - UNITS 1 & 2 6-11 l

I

.o '

3_

' ADMINISTRATIVE CONTROLS RECORDS (Continued) b.

Reports of reviews encompassed by Specification 6.5.2.8 above, shall be prepared, approved, and forwarded to the Vice President, Nuclear-

Production, and to the Executive Vice President, Power Group I

within 14 days following completion of the review; and c.

Audit reports encompassed by Specification 6.5.2.9 above, shall be forwarded to the Vice President, Nuclear Production, and to the Execu-tive Vice President, Power Group and to_the management positions l

responsible for the areas audited withir. 30 days after completion of-the audit by the auditing organization.

i 6.6 REPORTABLE EVENT ACTION

6. 6. '1 The following actions shall be taken for REPORTABLE EVENTS:

l a.

The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to-10 CFR Part 50 and b.

Each REPORTABLE EVENT shall be reviewed by the Station Manager; or by-(1) Operating Superintendent; (2) Technical Services Superintendent; (3) Maintenance Superintendent; or (4) Superintendent of Integrated Scheduling, as previously designated by the Station Manager, and the results of this review shall be submitted to the NSRB and the Vice' President-Nuclear Production.

C.7 snFETY LIMIT VIOLATION 6.7.1' The following actions shall be taken in the event a Safety Limit-is violated:

a.

The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

The Vice-President-Nuclear Production and the NSRB shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b.

A Safety Limit Violation Report shall be prepared.

The report shall be reviewed by the Operating Superintendent and Station Manager.

4 This-report shall describe:_ (1) applicable circumstances preceding.

the violation, (2) effects'of the violation upon facility components, systems,- or. structures, and (3) corrective action taken to prevent recurrence; c.

The Safety Limit Violation Report shall be submitted to the Commission, the-NSRB and the Vice President-Nuclear Production within 14 days of the violation; and d.

Critical operation of the unit shall not be resumed until authorized 4

by the Commission.

1 CATAWBA-- UNITS 1 & 2 6-12 Amendment No,80 (Unit 1)

Amendment No. 74 (Unit 2) a-

-.. ~ _ -.

ADMINISTRATIVE CONTF<0LS PROCEDURES AND PROGRAMS (Continued) e.

Post-Accident Sampling A program which will ensure-the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions.

The program shall include the following:

1)

Training-of personnel, 2)

Procedures for sampling and analysis,.and 3)

Provisions-for maintenance of sampling'and analysis equipment.

69 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements o'f Title 10, Code of Federal-Regulations, the following reports shall be submitted =to NRC in accordance with-10 CFR 50.4.

STARTUP' REPORT 6.9.'1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an Operating License, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear,

. thermal',-or hydraulic performance of the unit.

6.9.1.2. The Startup Report shall address each.of the tests' identified in the Final. Safety Analysis Report and.shall include a description of the measured values of the ? operating conditions or characteristics-obtained during the test program _and a comparison of these values with. design predictions and specifica--

tions.

Any corrective actions-that were required to obtain satisfactory operation shall also be described.' Any additional specific details required in license-conditions based on other commitments shall be included in this report, L~

6.9.1.3 Startup Reports shall be submitted within:

(1) 90 days following

> completion of the Startup Test Program,.(2) 90 days following resumption or commencement of commercial power operation, or (3) 9: months following initial-criticality,.whichever is earliest.

If the Startup Report does not cover all l

three events (i.e., initial criticality, completion of Startup Test Program, and resumption or commencement of commercial operation), supplementary reports 4

shall be submitted at least every 3 months until all three events have been completed.

L l

l

-CATAWBA --UNITS-1 & 2 6-15 Amendment No. 80 (Unit 1)

Amendment No. 74 (Unit 2)

l ADMINISTRATIVE CONTROLS SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT (Continued)

The Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radio-active materials in gaseous and liquid effluents made during the reporting period.

The Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and to the OFFSITE DOSE CALCULATION MANUAL (0DCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Specification 3.12.2.

MONTHLY OPERATING REPORTS 6.9.1.8 Routine reports of operating statistics and shutdown experience, in-cluding documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the NRC in accordance with 10 CFR 50.4, no l

later than the 15th of each month following the calendar month covered by the report.

CORE OPERATING LIMITS REPORT

6. 9.1. 9 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:

1.

Moderator Temperature Coefficient BOL and E0L limits and 300 ppm surveillance limit for Specification 3/4.1.1.3, 2.

Shutdown Bank Insertion Limit for Specification 3/4.1.3.5, 3.

Control Bank Insertion Limits for Specification 3/4.1.3.6, NO 4.

Axial Flux Difference Limits, target band, and APL for Specification 3/4.2.1, RTP ND 5.

Heat Flux Hot Channel Factor, F K(Z),W(Z),APL and W(Z)BL frSpecification3/4.2.3,a,nd NuclearEnthalpyRiseHotChannelFactor,FhP 6.

, and Power Factor Multiplier, MF3g, limits for Specification 3/4.2.3.

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by NRC in:

1.

WCAP-9272-P-A, " WESTINGHOUSE RELOAD SArETY EVALUATI0' METHODOLOGY,"

J July 1985 (W Proprietary).

(Methodology for Specifications 3.1.1.3 - Moderator Temperature Coef ficient, 3.1.3.5 - Shutdown Bank Insertion Limit, 3.1.3.6 - Control Bank Insertion Limits, 3.2.1 - Axial Flux CATAWBA - UNITS 1 & 2 6-19 Amendment No.80 (Unit 1)

Amendment No.74 (Unit 2) 1

w ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued)

Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 -

Nuclear Enthalpy Rise Hot Channel Factor.)

2.

WCAP-10216-P-A, " RELAXATION OF CONSTANT AXIAL OFFSET CONTROL FQ SURVEILLANCE TECHNICAL SPECIFICATION," June 1983 (W Proprietary).

(Methodology for Specifications 3.2.1 - Axial Flux Difference (Relaxed Axial Offset Control) and 3.2.2 - Heat Flux Hot Channel Factor (W(Z) surveillance requirements for F Methodology.)

q 3.

WCAP-10266-P-A Rev. 2, "THE 1981 VERSION OF WESTINGHOUSE EVALUATION MODEL USING BASH CODE," March 1987, (W Proprietary).

(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor.)

The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.

The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC in accordance with 10 CFR 50.4.

l CATAWBA - UNITS 1 & 2 6-19a Amendment No.80 (Unit 1)

Amendment No.74 (Unit 2)

l L

ADMINISTRATIVE CONTROLS SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the NRC in accordance with 10 CFR 50.4 within the time period specified for each report, 6.10 RECORD RETENTION 6.10.1 In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

The following records shall be retained for at least 5 years:

a.

Records and logs of unit operation covering time interval at each power level; b.

Records and logs of principal maintenance activities, inspections, repair, and replacement of principal items of equipment related to nuclear safety; c.

All REPORTABLE EVENTS; d.

Records of surveillance activities, inspections, and calibrations required by these Technical Specifications; e.

Records of changes made to the procedures required by Specification 6.8.1; f.

Records of radioactive shipments; g.

Records of sealed source and fission detector leak tests and results; and h.

Records of annual physical inventory of all sealed source material of record.

6.10.2 The following records shall be retained for the duration of the unit Operating License:

a.

Records and drawing changes reflecting unit design modifications made te systems and equipment described in the Final Safety Analysis Report; b.

Records of new and irradiated fuel inventory, fuel transfers, and assembly burnup histories; c.

Records of radiation expoture for all individuals enteir.J radiation control areas; d.

Records of gaseous and liquid radioactive material released to the environs; e.

Records of transient or operational cycles for those unit components identified in Table 5.7-1; f.

Records of reactor tests and experiments; g.

Records of training and qualification Ier current. members of the unit staff; 1

CATAWBA - UNITS 1 & 2 6-20 Amendment No.80 (Unit 1) 1 Amendment No. 74 (Unit 2)

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