Text

Amend 109 to License NPF-38,changing TS by Revising Administrative Controls Section of TS for Waterford 3 by Removing Functions Under Review & Audit from TS & by Relocating Items in QAPM
	ML20086H619
Person / Time
Site:	Waterford
Issue date:	07/06/1995
From:	Chandu Patel; NRC (Affiliation Not Assigned)
To:	;
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ML20086H622	List: ML20086H619; ML20086H644;
References
	NUDOCS 9507180211
	Download: ML20086H619 (15)
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UNITED STATES

,a j

NUCLEAR REGULATORY COMMISSION

's WASHINGTON, D.C. 20666 4 001

\\**.,*

ENTERGY OPERATIONS. INC.

DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATION. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 109 License No. NPF-38 1.

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

A.

The application for amendment by Entergy Operations, Inc. (the licensee) dated August 9, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

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

There is reasonable assurance (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 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 Commission's regulations and all applicable requirements have been satisfied.

i g71% M 2

P

t 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. NPF-38 is hereby amended to read as follows:

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.109, and the Environmental Protection Plan contained in Appendix 8, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance to be implemented within 60 days.

FOR THE NUCLEAR REGULATORY COMMISSION h 0 lCh P Chandu P. Patel, Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: July 6, 1995

4 ATTACHMENT TO LICENSE AMENDMENT NO.109 TO FACILITY OPERATING LICENSE NO. NPF-38 DOCKET NO. 50-382 Replace the following pages of the Appendix A Technical Specifications with the attached 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.

REMOVE PAGES INSERT PAGES 3/4 3-4 3/4 3-4 3/4 3-17 3/4 3-17 6-7 6-7 6-8 68 6-9 6-10 6-11 6-12 6-13 6-13 6-14 6-14 i

6-15 6-15 6-22 6-22 I

1 TABLE 3.3-1

-e m

REACTOR PROTECTIVE INSTRUMENTATION o=

MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE

)

FUNCf!ONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION I

x Z

1.

Manual Reactor Trip 2 sets of 2 1 set of 2

2. sets of 2 1 2 1

w 2 sets of 2 1 set of 2 2 sets of 2 3, 4*,

5*

8 I

2.

Linear Power Level - High 4

2 3

1,.2 2#, 3#

3.

Logarithmic Power Level-High Startup and Operating 4

2(a)(d) 3 2**

2#, 3#

a.

4 2

3 3*, 4*, 5*

8 b.

Shutdown 4

0 2

3,4,5 4

4.

Pressurizer Fressure - High 4

2 3

1, 2 2#, 3#

y 5.

Pressurizer Pressure - Low 4

2(b) 3 1, 2 2#, 3#

6.

Containment Pressure - High 4

2 3

1, 2 2#, 3#

w 7.

Steam Generator Pressure - Low 4/SG 2/SG 3/SG 1, 2 2#, 3#

8.

Steam Generator Level - Low 4/SG 2/SG 3/SG 1, 2 2#, 38 9.

Local Power Density - High 4

2(c)(d) 3 1, 2 2#, 38

10. DNBR - Low 4

2(c)(d) 3 1, 2 2#, 38

11. Steam Generator Level - High 4/SG 2/SG(g) 3/SG 1, 2 2#, 38

12. Reactor Protection System Logic 4

2 3

1 2 5

3E I

3, 4*, 5*

8 5

13. Reactor Trip Breakers 4

2(f) 4 1 2 5

ih A

N 3, 4*, 5*

8

14. Core Protection Calculators 4

2(c)(d) 3 1, 2 28, 3# and 7

15. CEA Calculators 2

1 2(e) 1, 2 6 and 7 M

16. Reactor Coolant Flow-- Low 4/SG 2/SG(c) 3/SG 1, 2-2#, 3#

l E

9

... a.

m m

vr

-v-

TABLE 3.3-1 (Continued)

TABLE NOTATION

With the protective system trip breakers in the closed position, the CEA drive system capable of CEA withdrawal, and fuel in the reactor vessel.

The provisions of Specification 3.0.4 are not applicable.

- Not applicable above 10% RATED THERMAL POWER.

(a) Trip may be manually bypassed above 10% of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is less than or equal to 10% of RATED THERMAL POWER.

(b) Trip may be manually bypassed below 400 psia; bypass shall be auto-matica11y removed whenever pressurizer pressure is greater than or equal to 500 psia.

(c) Trip may be manually bypassed below 10% of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is greater than or equal to 10% of RATED THERMAL POWER. During testing pursuant to Special Test Exception 3.10.3, trip may be manually bypassed below 5% of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is greater than or equal to 5% of RATED THERMAL POWER.

(d) Trip may be bypassed during testing pursuant to Special Test Exception 3.10.3.

(e) See Special Test Exception 3.10.2.

(f)

Each channel shall be comprised of two trip breakers; actual trip logic shall be one-out-of-two taken twice.

(g) High steam generator level trip may be manually bypassed in Modes 1 and 2, at 20% power and below.

ACTION STATEMENTS ACTION 1 With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and/or open the j

protective system trip breakers.

ACTION 2 With the number of channels OPERABLE one less than the Total Number of Channels, STARTVP and/or POWER OPERATION may continue provided the inoperable channel is placed in the bypassed or tripped condition within I hour.

If the inoperable channel is bypassed, the desirability of maintaining this channel in the bypassed condition shall be documented by the Plant Operations Review Committee in accordance with plant administrative procedures.

The channel shall be returned to OPERABLE status prior to STARTVP following the next COLD SHUTDOWN.

WATERFORD - UNIT 3 3/4 3-4 AMENDMENT N0. 4h40,109 i

TABLE 3.3-3 (Continued)

TABLE NOTATION (a) Trip function may be bypassed in this H0DE when pressurizer pressure is less than 400 psia; bypass shall be automatically removed when pressurizer pressure is greater than or equal to 500 psia.

(b) An SIAS signal is first necessary to enable CSAS logic.

The provisions of Specification 3.0.4 are not applicable.

ACTION STATEMENTS ACTION 12 -

With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 13 -

With the number of channels OPERABLE one less than the Total Number of Channels, STARTUP and/or POWER OPERATION and/or opera-tion in the other applicable MODE (S) may continue provided the inoperable channel is placed in the bypassed or tripped condition within I hour.

If the inoperable channel is bypassed, the desirability of maintaining this channel in the bypassed condition shall be documented by the Plant Operations Review Committee in accordance with plant administrative procedures.

The channel shall be returned to OPERABLE status no later than prior to entry into the applicable MODE (S) following the next COLD SHUTDOWN.

With a channel process measurement circuit that affects multiple functional units inoperable or in test, bypass or trip all associated functional units as listed below:

Process Measurement Circuit Functional Unit Bypassed / Tripped 1.

Containment Pressure - High Containment Pressure - High (ESF)

Containment Pressure - High (RPS) 2.

Steam Generator Pressure -

Steam Generator Pressure - Low Low Steam Generator oP 1 and 2 (EFAS) 3.

Steam Generator Level Steam Generator Level - Low Steam Generator Level - High Steam Generator oP (EFAS)

WATERFORD - UNIT 3 3/4 3-17 AMENDMENT NO.109

_ TABLE 3.3-3 (Continued)

TABLE NOTATION ACTION 14 -

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE, STARTUP and/or POWER OPERATION and/or opera-tion in the other applicable MODE (S) may continue provided the following conditions are satisfied:

Verify that one of the inoperable channels has been bypassed a.

and place the other inoperable channel in the tripped-condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

b.

All functional units affected by the bypassed / tripped channel shall also be placed in the bypassed / tripped condition as listed below.

I Process Measurement Circuit Functional Unit Bypassed / Tripped 1.

Containment Pressure Circuit Containment Pressure - High (EST)

Containment Pressure - High (RPS) 2.

Steam Generator Pressure -

Steam Generator Pressure - Low Low Steam Generator Level - High Steam Generator AP (EFAS) 3.

Steam Generator Level Steam Generator Level -Low Steam Generator Level - High Steam Generator AP (EFAS)

STARTUP and/or POWER OPERATION and/or operation in the other applicable MODE (S) may continue until the performance of the next required CHANNEL FUNCTIONAL TEST.

Subsequent STARTUP and/or POWER OPERATION and/or operation in the other applicable MODE'(S) may continue if one channel is restored to OPERABLE status and the provisions of ACTION 13 are satisfied.

ACTION 15 -

With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channels to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 16 -

With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the associated valve inoperable and take the ACTION required by Specification 3.7.1.5.

ACTION 17 -

With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may continue provided the inoperable channel is placed in the tripped (D.C.

Relay energized) condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , the remaining Emergency Diesel Generator is OPERAB).E, and the inoperable channel is restored to OPERABLE status within the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

Otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

The surveillance requirements of Table 4.3-2 are waived for all channels while this action requirement is in effect.

L.

ADMINISTRATIVE CONTROLS 4

6.3 UNIT STAFF OUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI /ANS 3.1-1978 except that:

The Radiation Protection Superintendent shall meet or exceed the a.

minimum qualifications of Regulatory Guide 1.8, September 1975.

b.

Personnel in the Health Physics, Chemistry and Radwaste Departments shall meet or exceed the minimum qualifications of ANSI N18.1-1971.

The licensed Operators and Senior Operators shall also meet or exceed c.

the minimum qualifications of 10 CFR Part 55, d.

Personnel in the Nuclear Quality Assurance Department, and other staff personnel who perform inspection, examination, and testing functions, shall meet or exceed the minimum qualifications of Regulatory Guide 1.58, Rev. 1, September 1980.

(Endorses ANSI N45.2.6-1978).

6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Training _ Manager-Nuclear and shall meet or exceed the requirements and recommendations of Section 5.2 of ANSI 3.1-1978 and 10 CFR Part 55.

6.5 Not used.

1 l

WATERFORD - UNIT 3 6-7 AMENDMENT NO. 18,43,51,53,70,109

h Paaes 6-9 throuch D8Q0 6-12 not used i

WATERFORD - UNIT 3 6-8 AMENDMENT NO. 18,53,79,10ccio9 Next page is 6-13

ADMINISTRATIVE CONTROLS I

6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

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 Plant Operating Review Committee (PORC) and the results of this review shall be submitted to the Safety Review Committee (SRC) and the Vice President Operations.

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

WATERFORD - UNIT 3 6-13 AMENDMENT NO. 4853,100,l 10d

ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION (Continued)

The NRC.0perations Center shall be notified by telephone as 'soon as a.

possible and in all cases within I hour. The Vice President Opera-tions and the SRC shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

A Safety Limit Violation Report shall be prepared.

The report shall be reviewed by the PORC. 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 SRC and the Vice President Operations within 14 days of the violation.

d.

Critical operation of the unit shall not be resumed until authorized by the Commission.

6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

The applicable procedures recommended in Appendix A of Regulatory a.

Guide 1.33, Revision 2, February 1978 and Emergency Operating Procedures required to implement the requirements of NUREG-0737 and NUREG-0737, Supplement 1, as stated in Generic Letter 82-33.

b.

Refueling operations.

Surveillance and test activities of safety-related equipment.

c.

d.

Not used.

e.

Not used.

f.

Fire Protection Program implementation.

g.

Modification of Core Protection Calculator (CPC) Addressable Constants, including independent verification of modified constants.

NOTES:

(1) Modification to the CPC addressable constants based on information obtained through the Plant Computer - CPC data link shall not be made without prior approval of the PORC.

(2) Modifications to the CPC software (including algorithm changes and changes in fuel cycle specific data) shall-be performed in accordance with the most recent version of CEN-39(A)-P, "CPC Protection Algorithm Software Change _ Procedure," that has been determined to be applicable to the facility. Additions or deletions to CPC Addressable Constants or changes to Addressable Constant software limits values shall not be implemented without prior NRC approval, h.

Administrative procedures implementing the overtime guidelines of Specification 6.2.2e., including provisions for documentation of deviations.

i.

PROCESS CONTROL PROGRAM implementation.

WATERFORD - UNIT 3 6-14 AMENDMENT NO. 5,51,53,100, 109

ADMINISTRATIVE CONTROLS 3

v.

ERQGEDURES AND PROGRAMS (Continued)-

j..

OFFSITE DOSE CALCULATION MANUAL implementation, k.

Quality Assurance Program for effluent and environmental monitoring, using the guidance in Regulatory Guide 1.21, Revision 1, June 1974 and Regulatory Guide 4.1, Revision 1, April 1975.

6.8.2 Each procedure of Specification 6.8.1, and changes thereto, shall be P

reviewed and approved prior to implementation and reviewed periodically as set l forth in' administrative procedures.

i 6.8.3 Temporary changes to procedures of Specification 6.8.1 may be made provided:

The intent of the original procedure is not altered; a.

b.

The change is approved by two members of the plant management staff, at least one of whom holds a Senior Operator license on the unit

affected, 1

The change is documented, reviewed and approved as required by c.

administrative procedures within 14 days of implementation.

l-6.8.4 The following programs shall be established, implemented.and maintained:

a.

Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include the containment spray, safety injection, hydrogen analyzer, and the post-accident sampling system.

The program shall include the following:

1.

Preventive maintenance and periodic visual inspection requirements, and 2.

Integrated leak test requirements for each system at refueling cycle intervals or less.

b.

In-Plant Radiation Monitorina A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident-conditions. This program shall include the following:

l i

WATERFORD - UNIT 3 6 AMENDMENT NO. 53,100,109

1 ADMIN 157RATIVE CONTROLS PROCEDURES AND PROGRMS (Continued) 3.

Training of personnel, Proceduresfor[ monitoring,and 2.

3.

Provisions for maintenance of sampling and analysis equipment.

c.

Secondary Water themistry A program for monitoring of secondary water chesistry to inhibit steam generator tube degradation. This program shall include:

1.

Identification of a sampling schedule for the critical variables and control points for these variables, 2.

Identification of the procedures used to esasure the values of the critical variables, 3.

Identification of process sampling points, which'shall include monitoring the discharge of the condensate pumps for evidence of condenser in-leakage, 4.

Procedures for the recording and management of data, 5.

Procedures defining corrective actions for all off-control point chemistry conditions, and 6.

A procedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action.

d.

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

The program shall include the following:

3.

Training of personnel, 2.

Procedures for sampling and analysis, and 3.

Provisions for maintenance of sampling and analysis equipment, e.

Baseest Monit'orine i

A program for monitoring of the Nuclear Plant Island Structure i

(NP15) Comon Foundation Basemat to ensure the continued integrity of the Basemat. The program shall include:

l t

1.

settlement of the basemat 2.

changes in ground water cheelstry that could effect corrosion of reinforcing steel l

3.

seasonal variation in ground water levels l

4.

monitoring of significant cracking in the basemat.

l WATERFORD - UNIT 3 6-16 Anndment No. 82 l

ADMINISTRATIVE CONTROLS 4

RECORD RETENTION (Continued) 6.10.2 The following records shall be retained for at least 5 years:

Records and. logs of unit operation covering time interval at each a.

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.

Records of surveillance activities; inspections, and calibrations d.

required by these Technical Specifications.

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

e.

f.

Records of radioactive shipments.

Records of sealed source and fission detector leak tests and results g.

h.

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

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

l Records and drawing changes reflecting' unit design modifications a.

made to 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 exposure for all individuals entering radiation l

control areas.

d.

Records of gaseous and liquid radioactive material released to the

environs, Records of transient or operational cycles for those unit components e.

identified in Table 5.7-1.

f.

Records of reactor tests and experiments.-

I Records of training and qualification for current members of the g.

unit staff, h.

Records of inservice inspections performed pursuant to these Technical Specifications.

UATERFORD - UNIT 3 6-21

p ADMINISTRATIVE CONTROLS

' RECORD RETENTION'(Continued) 1.

Records of quality assurance activities required by the Quality Assurance Program Manual.

~j.

Records of reviews performed for changes made to procedures or equip-L ment or reviews of tests and experiments pursuant.to 10 CFR 50.59.

s

'k.

Records.of meetings of the PORC and the SRC.

1.

Records of the service lives of all hydraulic and mechanical snubbers required by Specification 3.7.8 including the date at which the service life commences and associated installation and maintenance records.

Records of secondary water sampling and water quality, m.

n.

DELETED.

l o.

Records of analyses required by the radiological environmental monitoring program that would permit evaluation of the accuracy of the analysis at a later date. This should include procedures effective at specified times and QA records showing that these procedures were followed.

p.

Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

6.11 RADIATION PROTECTION PROGRAM 6.11.1 Procedures for personnel radiation protection shall be prepared consis-tent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR Part 20, each high radiation area in which the intensity of radiation is greater'than 100 mrem /h_but less than 1000 mrem /h shall be barricaded and conspicuously posted as a high. radiation area and entrance j

thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP)*. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:'

A radiation monitoring device which continuously indicates the a.

radiation dose rate in the area.

i

Health physics personnel or personnel e'scorted by health physics personnel.

shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they are otherwise following-plant radiation protection procedures for entry into high radiation areas.

WATERFORD - UNIT 3 6-22 AMENDMENT NO. 68,109-

_ - _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _

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