ML13326A661

Amend 58 to License DPR-13,reflecting Tech Spec Changes Incorporating TMI-2 Lessons Learned Category a Requirements

ML13326A661
Person / Time
Site:	San Onofre
Issue date:	11/06/1981
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:
Shared Package
ML13326A660	List: ML13326A659 ML13326A661 ML13326A662 ML13326A663
References
DPR-13-A-058, TAC-44128, TASK-***, TASK-TM NUDOCS 8111300183
Download: ML13326A661 (18)

Text

1,0~

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO,AS

& ELECTRIC. COMPANY DOCKET NO. 50-206 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 58 License No.

DPR-13

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

A. The application for amendment by Southern California Edison Company and San Diego Gas and Electric Company (the licensees) dated May 7, 1981, 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 10CFR 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.

PDR ADOCK 05000206 PDR)

-.2

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and-Paragraph 3.B of Provisional Operating Li.cense No. DPR-13 is hereby amended to read as follows:

B. Technical Specifications The-Technical Specifications contained in Appendices A and B, as revised through Amendment No. 58, are hereby incorporated in.the license.. Southern California Edison Company shall operate the facility in accordance with the Technical Specifi cations.

3. This-license amendment is effective 30 days from the-date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Dennis M.

Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: November 6, 1981

Table 4 T (cont'd)

No.

Channels Action Minimum Frequency

14.

Residual Heat Pump Flow Calibration At each refueling shutdown,

15.

Refueling Tank Level

'.Calibration At each refueling shutdown Test Once per month during operation

16.

Volume Control Tank LeVel Calibration At each refueling shutdown Test Once per month during operation

17.

Deleted

18. Area Radiation Monitors Calibration Once per month Test Once per day

19.

Hydrazine Tank Level Calibration At each refueling shutdown Test One per month during operation Amendment No. r 5

. 58

-33j 3.5.5 Containment Isolation Instrumentation Applicability: Applies to instrumentation which actuates the containment sphere isolation valves, containment sphere purge and exhaust valves, and containment sphere instrumentation vent header valves.

Objective:

To ensure reliability of the containment sphere isolation provi si ons.

Specification:

A. The instrumentation channels shown in Table 3.5.5-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.5.5-2.

8. With an. instrumentation channel trip setpoint less conservative than the Allowable Values column of Table 3.5.5-2, declare the channel inoperable-and apply the applicable Action requirement of Table 3.5.5-1.until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setpoint Value.

C. With an instrumentation channel inoperable, take the action shown in Table 3.5.5-1.

Basis:

The operability of these instrumentation systems.ensure that

1) the associated action will be initiated when the parameter monitored by each channel or combination thereof reaches its setpoint, 2) the specified coincidence logic is maintained, 3) sufficient redundancy is maintained to permit a channel to be out of service for testing or maintenance, and 4) sufficient system functional capability is available from diverse parameters.

The operability of these systems is required to provide the overall reliability, redundancy, and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions. The integrated operation of each of these systems is consistent with the assumptions used in the accident analyses.

References:

(1) NRC letter dated July 2, 1980, from D. G. Eisenhut to all pressurized water reactor licensees.

Amendment No.

58

TAIBLE 3.S.1 INSTRUMENT OPERATING CONDITIONS COLUMN I COLUMN i1 COLUMN III Minimm Operational Ninimum hedund0no7 Required Opering Acklen if Channels Required ColumnI or Colon 11 Functional Unit Cannot be het 1 Nuotear owser-Critioal For 3-Channel Maintain hotatathdby conitioham.

Operation -t For 4 Channel operation

.SubritiOe hetnln ho atandbyit dt least one source and one Intermediate chanhel are availables otherwie maintel 10% Ak/k shutdown earate.

2 Pressuriser Variable Maintain load below 101 F.*P.

Low Pressure Pressurizer Fixed High Pressure Maintain hot standbv oonditiobs.

4.

Pressuriser High Level a

Mdintals hot stahdby conditions.

Reotor Coolant Flow 3-otop operation oad below 10 F. P.

6* Ieted.

Redundanoy ia defined as N-M.

wherO N is the nuber of hannels In oertion, and N is the nmber or ahannels In opration whish, when tripped,will ause an autoati shutdown.

.-For operation at (50% of full power 0 seFor operation at Y50% of full power*

(51

TABLM 3.-. (continued) tastaunrt OPERATIN0 CONDITI0ON COWM III COHIMf I COWI t

RequireG Operating Action if Milama Operational Minismm Redundanc Coluim I or Volumn II F"Unctions t

Channels Aequired

('annt be-Met Deleted.

. anual Trip ainta botatandby conditions.

9*

)eleted.,

10.

tees Feed-ater Flor mstch Operatot shall aese contiuea b" surv.illamce and aetuate manual serm It required.

• !3eunani g erined as 3-N were is. the matber-of cannelin Pration&-and N is the number ofudac ahneO pp~ato hc.we tr~pyeda will cause an automatic ahutdown.

\\,

IN0

-331 TABLE 3.5.5-1 (Continued)

TABLE NOTATION ACTION STATEMENTS ACTION A - With the number of OPERABLE channels one less than the Total Number of Channels, be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the followin 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />; however, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.1.4.

ACTION B -

With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed until performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

ACTION C -

With less than the Minimum Channels OPERABLE, operation may continue provided the containment purge and exhaust valves (POV-9 &

POV-10) are maintained closed.

ACTION D -

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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

Amendment No. 58

1 9a.

3.1.5 Pressurizer Relief Valves Appli'cability: Applies to the power operated relief valves (PORVs) and their associated block valves for MODES 1, 2 and 3.

Objective:

To ensure reliability of the PORVs and block valves.

Specification:

A. Two PORVs and their associated block valves shall be OPERABLE.

B. With one or more PORV(s) inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV(s) to OPERABLE status or close the associated block valve(s) and remove power from the block valve(s); otherwise, 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

C. With one or more block valve(s) inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

either restore the block valve(s) to OPERABLE status or close the block valve(s) and remove power from the block valve(s); otherwise, 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.,

Basis:

The power operated relief valves (PORVs) operate to relieve RCS pressure below the setting of the pressurizer code safety valves. These relief valves have remotely operated block valves to provide a positive shutoff capability should a relief valve become.inoperable. The air supply for both the relief valves and the block valves is capable of being supplied from a backup passive nitrogen source to ensure the ability to seal this possible RCS leakage path.

References:

(1) NRC letter dated July 2, 1980, from D. G. Eisenhut to all pressurized water reactor licensees.

Amendment No. 58

lb TABLE 1.1 FREQUENCY NOTATION NOTATION FREQUENCY(1)

S At'Teast once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

D Ai least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

w At least once per 7 days.

BW At least once per 14 days.

At least once per 31 days.

Q At least once per 92 days.

SA At least once per 184 days.

R At least once per 18 months.

S/U Prior to each reactor startup.

P Completed prior to each release.

N.A.

Not applicable.

(1) For each frequency, the allowable extension is 25%. The total allowable extension for three consecutive frequency intervals is 3.25 times the interval.

Amendment No. 58.

ATTACHMENT TO LICENSE AMENDMENT NO. 58 PROVISIONAL OPERATING LICENSE NO. DPR-13 DOCKET NO. 50-206 Revised Appendix A Technical Specifications and Bases by removing the following pages and by inserting the enclosed pages.

The revised pages contain the captioned amendment number and marginal lines indicating the area of change.

REMOVE INSERT lb 18a 18b 29 29 30 30 33j -

33r 34 34 35a -

35c

42.

42 44b*

44c -

44k 47 47 48 48 51a -

51c 71

.71 72a 72a 88 88**

[89 (currently. unnumbered 89 and contains Section 6.12)]

• Merely reserves Section 4.1.3 for Technical Specifications which remain under review.

• • There are, no changes to the provisions contained on this page; it is merely included for, the purpose. of reformating. (Section 6.12)..

18b 3.1.6 Pressurizer Applicability: Applies to the pressurizer heaters and pressurizer water level for MODES 1, 2 and 3.

Objective:

To ensure that pressurizer heaters are available during a loss of offsite power condition.

Specification: A-The pressurizer shall b4 OPERABLEwith at least-125' kilowatts-of pressurizer heaters and a water level between 5 percent and 70 percent.

B. With the pressurizer inoperable due to the loss of capability to energize the pressurizer heaters from an emergency diesel generator, either restore the capability to energize the pressurizer heaters from an emergency diesel generator within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 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 HOT SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. With the pressurizer otherwise inoperable, be in at least HOT STANDBY with the reactor trip breakers open within 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> and in 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 />.

Basis:

The requirement that 125 kw of pressurizer heaters and their associated controls be capable of being supplied electrical power from an emergency diesel generator provides assurance that these heaters can be energized during a loss of offsite power condition to maintain natural circulation at HOT STANDBY.

References:

(1) NRC letter dated July 2, 1980, from D. G. Eisenhut to all pressurized water reactor licensees.

(2) SCE letter dated October 17, 1979, from J. H. Drake to D. G. Eisenhut, "Responses to NRC Requirements Related to the Three -Mile Island Accident," Item 2.1.1 of the enclosure.

35c 3.6.3 Hydrogen Monitors and Hydrogen Recombiners Applicability:

Applies to containment sphere hydrogen monitors and hydrogen recombiners for MODES 1 and 2.

Objective:

To ensure the capability tormaintain the hydrogen concentration within the containment sphere below its flammable limit-during post-LOCA conditions..

Specification:

A. Two independent containment hydrogen monitors shall be OPERABLE.

B. With one hydrogen monitor inoperable, restore the inoperable monitor to OPERABLE status within 30 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 />.

C. Two independent containment hydrogen recombiner systems shall be OPERABLE.

D. With one hydrogen recombiner system inoperable, restore the inoperable system to OPERABLE status within 30 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 />.

Basis:

The OPERABILITY of the equipment and systems required for the detection and control of hydrogen gas ensures that this equipment will be available to maintain the hydrogen concentration within containment below.its flammable limit during post-LOCA conditions. Either recombiner unit (or the purge system) is capable of controlling the expected hydrogen generation associated with radiolytic decomposition of water and corrosion of metals within containment.

(Cumulative operation of the purge system with the heaters on for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over a 31-day period is,sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters.) These hydrogen control systems are consistent with the recommendations of Regulatory Guide 1.7, "Control of Combustible Gas Concentrations in Containment Following a LOCA," March 1971.

The hydrogen mixing systems are provided to ensure adequate mixing of the containment atmosphere following a.LOCA. This mixing action will prevent localized accumulations of'hydrogen.

from exceeding the flammable limit.

References:

(1) Regulatory Guide 1.7, "Control of Combustible Gas Concentrations in Containment Following a LOCA,"

March,. 1971.

TABLE 3.5.5-1 CONTAINMENT ISOLATION INSTRUMENTATION MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION Containment Isolation (Valves listed in Table 3,6.2-1) a) Manual 2

1 2

1, 2, 3, 4 D

b) Containment Pressure-High 3/train 2/train 2/train 1, 2, 3 B

c) Sequencer Subchannels 2/sequencer 2/sequencer 2/sequencer 1, 2, 3, 4 A

d) Safety Injection

1) Containment Pressure-High 3/train 2/train 2/train 1, 2,3 B

(0

2) Pressurizer Pressure-Low 3/train 2/train 2/train 1, 2, 3 B

'Purge and Exhaust Isolation (POV-9, POV-10, CV-10, CV-40, CV-116) a) Manual 1

1 1

1, 2, 3, 4 C

b) Containment 1

1 1

1, 2, 3, 4C Radioactivity-High

TABLE 3.5.5-2 CONTAINMENT ISOLATION INSTRUMENTATION TkIP SET POINTS FUNLTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES Containment Isolation a) Manual Not Applicable NotApplicable b) Containment Pressure-High 51.4 psig

2.0 psig c) Sequencer Subchannels Not Applicable Not Applicable d) Safety Injection

1) Containment Pressure-High

<1.4 psig

Z.0 psig

2) Pressurizer Pressure-Low 1685 psig 1675 psig

.(D Purge and Exhaust Isolation o

0, a) Manual Not Applicable Not Applicable b) Containment Radioactivity-High x Background.2.5 x Background

-33n.

3 5.6 Accident Monitoring Instrumentation Ap.plicability: Applies to the accident monitoring instruments shown in Table 3.5.6-1 for MODES 1, 2 and 3.

Objective:

To ensure reliability of the accident monitoring instrumentation.

Specification A. The accident-monitoring instrumentation channels shown in Table,3.5.6-1 shall be OPERABLE.

B. With the number of OPERABLE accident monitoring instrumentation channels less than the Total Number of Channels shown in Table 3.5.6-1, either restore the

-inoperable-channel(s) to OPERABLE status within 7 days, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

C. With the number of OPERABLE accident monitoring instrumentation channels less than the MINIMUM CHANNELS OPERABLE requirements of Tabel 3.5.6-1, either restore the inoperable channel(s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Basis:

The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables during and following an accident. This capability is consistent with the recommendations of Regulatory Guide 1.97, "Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1975 and NUREG-0578, "TMI-2 Lessions Learned Task Force-Status Report and Short-Term Recommendations."

References:

(1) NRC letter dated July 2, 1980, from D. G. Eisenhut to all pressurized water reactor licensees.

Amendment No. 58

3.6.2 Containment Isolation Valves Applicability: Applies to the containment isolation valves listed in Table 3.6.2-1 for MODES 1, 2, 3-and 4.

Objective:

To provide assurance that containment isolation will function when initiated by appropriate sensors.

Specification:

A-The containment isolation valves specified in Table 3.6.2-1 shall be OPERABLE.

B. With one or more of the isolation valve(s) specified'in Table 3.6.2-1 inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and either:

1.

Restore the.inoperable valve(s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or

2.

Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position, or

3. Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual valve or blind flange, or

4. 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

Basis:

The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of, the containment.

Containment isolation ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.

References:

(1)

NRC letter dated July 2, 1980, from D. G. Eisenhut to all pressurized water reactor licensees.

TABLE 3.5.6-1 ACCIDENT MONITORING INSTRUMENTATION MINIMUM TOTAL NO.

CHAINELS INSTRUMENT OF CHANNELS OPERABLE Pressurizer Water Level 3

2 Auxiliary Feedwater Flow Indication*

2 per steam generator 1 per steam generator Reactor Coolant System Subcooling Margin Monitor 2

1 PORV Position Indicator (Limt Switch) 1/valve 1/valve PORV Block Valve Position Indicator (Limit Switch 1/valve 1/valve Safet, Valve Position Indicator (Limit Switch) 1/valve 1/valve CD

• Auxiliary feedwater flow indication for each steam generator is provided by one channel of steam generator level and one channel of auxiliary feedwater flow rate. These comprise the two channels of auxiliary feedwater flow indication for each steam generator.

00*

-. '3 3 p-.

3.5.7 Auxiliary Feedwater Instrumentation Applicability: Applies to automatic initiation of the auxiliary feedwater pumps.

Objective:

To ensure reliability of automatic initiation of the auxiliary feedwater pumps.

Specification: A. The instrumentation channels shown in Table 3.5.7-1 shall be OPERABLE with their trip setpoints set consistent with the Trip Setpoint column of Table 3.5.7-2.

B. With an instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.5.7-2, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.5.7-1 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setpoint Value.

C. With one instrumentation channel inoperable, take the action shown in Table 3.5.7-1.

D. With more than one channel inoperable, take ACTION G of Table 3.5.7-1.

Basis:

The OPERABILITY of the auxiliary feedwater instrumentation ensures that 1) the associated action will be initiated when the parameter monitored by each channel or combination thereof reaches its setpoint, 2) the specified coincidence logic is maintained, 3) sufficient redundancy is maintained to permit a channel to be out of service for testing or maintenance, and

4) sufficient system functional capability is available from diverse parameters.

The OPERABILITY of this instrumentation is required to provide the overall reliability, redundancy, and diversity assumed available for the protection and mitigation of accident and transient conditions. The operation of this instrumentation is consistent with the assumptions used in the accident analyses.

References:

(1) NRC letter dated July 2, 1980, from D. G. Eisenhut to all pressurized water reactor licensees.

Amendment No. 58