Text

Amends 117 to Licenses DPR-32 & DPR-37,respectively, Changing Tech Spec Sections 3.7 & 4.1 Re Instrumentation Sys & Operational Safety Review to Bring Them Into Closer Agreement W/Westinghouse STS & to Conform W/Nrc Guidance
	ML20149K058
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Site:	Surry
Issue date:	02/17/1988
From:	Berkow H; Office of Nuclear Reactor Regulation
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UNITED STATES

!" 3 m ',i NUCLEAR REGULATORY COMMISSION j

WASHINGTON, D. C. 20655 j

\\...../

VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION, UNIT N0. 1 j

AMENDMENT TO FACILITY OPERATING LICENSE

/cendment No.117 License No. DPR-32

)

1.

The Nuclear Regulatory Comission (the Comissioni has found that:

A.

The application for amendment by Virginia Electric and Power Company (the licensee) dated October 31, 1985, as superseded September 25, 1986 and May 22, 1987; and the application dated April 12, 1985, as revised September 9,1985 and October 7,1985, and superseded September 25, 1986, and May 22, 1987, and as supplemented October 23, 1987, comply with the standards and requirements of the Atomic Energy Act of 1954, as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 confonnity with the application, the provisions of the Act, and the rules and regulations of the Comission; l

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; D.

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

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

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No. DPR-32 is hereby amended to read as follows:

i P

-,l

l

.p-(B) Technical Specifications The Technical Specifications contained in Appendix A, as itsised thrcugh Amendment No.117, are hereby 1

incorporated in the license.

The licensee shall cperate the facility in accordance with the Technical Specifications.

3.

This license amendrent is effective as of the date of its issuarce, and shall be implemented within 30 days from the date of its issuance.

FOR HE NUCLEAR REGULATORY CCFFISSION v-Ferbert N. Berkow, Director Project Directorate II-?

Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Cate of Issuance:

February 17, 1988

p* * * %q'o UNITED STATES l'

NUCLEAR REGULATORY COMMISSION j

t WASHINGTON, D. C. 20555 j

\\...../

VIRGINIA ELECTRIC AND POWER COMPANY 1

DOCKET NO. 50-281 SURRY POWER STATION, UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE

/cendment No.117 License No. OPR-37 1.

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

A.

The application for amendment by Virginia Electric and Power Company (the licensee) dated October 31, 1985, as superseded September 25, 1986 ar. 'ay 22, 1987; and the apolication dated April 12, 1985, as revisei. ' ptember 9,1985 and October 7,1985, and superseded Seotemt 25, 1986, and May 22, 1987, and as supplemented October 23, 1987, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

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

There is reasonable assurance (1) 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; l

D.

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

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

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 Facility Operating License No. OPR-37 is hereby amended to read as follows:

i

~

2 (B) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.117. are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance, and sha'.1 be implemented within 30 days from the date of its issuance.

FOR THE NUCLEAR REGULATORY COMM:SSION erbert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation At' chment:

Changes to the Technical Specifications Cate of Issuance:

February 17, 1788 4

ATTACHMENT TO LICENSE AMENDPENT AMEN 9 MENT NO. 117 FACILITY OPERATING LICENSE NO. DPR-32 AMENDMENT N0. 117 FACILITY OPERATING LICENSE NO. OPR-37 4

DOCKET NOS. 50-280 AND 50-281 Revise Appendix A as follows:

Remove Pages Insert Pages TS 3.7-1 TS 3.7-1 TS 3.7-2 TS 3.7-2 TS 3.7-10 TS 3.7-10 TS 3.7-11 TS 3.7-11 TS 3.7-12 TS 3.7-12 TS 3.7-13 TS 3.7-13 TS 3.7-13a TS 3.7-13b TS 3.7-13c TS 3.7-13d i

TS 4.1-1 TS 4.1-1 i

TS 4.1-6 TS 4.1-6 TS 4.1-7 TS 4.1-7 TS 4.1-8 TS 4.1-8 TS 4.1-8a TS 4.1-8a TS 4.1-8b TS 4.1-8b TS 4.1-8c TS 4.1-8c TS 4.1-8d TS 4.1-9 TS 4.1-9 l

i

TS 3.7-1 3.7 INSTRUMENTATION SYSTEMS Operational Safety Instrumentation Applicability Applies to reactor and safety features instrumentation systems.

Objectives To provide for automatic initiation of the Engineered Safety Features in the event that principal process variable limits are

exceeded, and to delineate the conditions of the plant instrumentation and safety circuits necessary to ensure reactor safety.

Specification A.

For on-line testing or in the event of a subsystem instrumentation channel f ailure, plant operation at rated power shall be pe rmit ted to continue in accordance with TS Tables 3.7-1 through 3.7-3.

B.1 The reactor trip system inst rumentation channels shall be operable as specified in TS Table 3.7-1.

B.2 In the event the number of channels of a particular subsystem I in service falls below the limite given in the column entitled Minimum Operable Channels or Minimum Degree of Redundancy cannot be achieved, operation shall be limited according to the requirement shewn in Column 4 of TS Tables 3.7-2 and 3.7-3.

Amendnent !!os.117 and 117

TS 3.7-2 C.

In the event of subsystem ins t rumentation channel failure permitted by Specification 3.7.B2, Tables 3.7-2 and 3.7-3 need not be obse rved during the short period of time an operable subsystem channel is tested where the failed channel must be blocked to prevent unnecessary reactor trip.

D.

The Engineered Safety Features initiation inst rumenta tion setting limits shall be as stated in TS Table 3.7-4.

E.

The radioactive liquid and gaseous effluent monitoring instrumentation channels shown in Table 3.7-5(a) and Table 3.7-5(b) shall be operable with their alarm / trip setpoints set to ensure that the limits of Specifications ~3.11.A.1 and 3.11.B.1 are not exceeded.

The alarm trip setpoints of these channels shall be determined and adjusted in accordance with the Offsite Dose Calculation Manual (ODCM).

1.

With a radioactive liquid or gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specification, without delay suspend the release of radioactive liquid or gaseous effluents monitored by the affected channel and declare the channel inoperable or change the setpoint so it is acceptably conservative.

2.

With less than the minimum number of radioactive liquid or gaseous effluent monitoring ins t rumentation channels operable, take the action shown in Tabl6 3.7-5(a) or Table 3.7-5(b).

Exert best ef forts to return the instruments to operable status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a tieely manner.

f.mendment Mos. 117 and 117

TABI.E 3.7-I REACTOR TRIP INSTRIIMENT OPERATING CONDITIONS MINIMIIM TOTAI. NUMBER OPERABI.E CilANNEI.S PERMISSIBI.E FUNCTIONAL, UNIT OF CIIANNEI.S CilANNEI.S TO TRIP RYPASS CONDITIONS OPERATOR ACTION

1. Manual 2

2 I

I

2. Nuclear Flux Power Range 4

3 2

I,ow trip setting at P-10 2

3. Nuclear Flux Intermediate 2

2 1

P-10 3

Range

4. Nuclear Flux Source Range P-6 A. Below P Note A 2

2 1

4 B. Shutdown - Note B 2

1 0

5

5. Overtemperature AT 3

2 2

6

6. Overpower AT 3

2 2

6

7. Iow Pressurizer Pressure 3

2 2

P-7 7

8. Hi Pressurizer Pressure 3

2 2

7 Note A - With the reactor trip breakers closed and the control rod drive system capable of rod withdrawal

~S Note B - With the reactor trip breakers open ct a

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TAIILE 3.7-1 REACTOR TRIP INSTRIHENT OPERATING CONDITIONS MINIMUM TOTAL NUMBER OPERABI.E CilANNELS PERMISSIBl.E FUNCTIONAL UNIT OF CHANNELS CilANNELS TO TRIP BYPASS CONDITIONS OPERATOR ACTION _

17. Low steam generator water 2/ loop-level I/ loop-level I/ loop 7

Icvel with steam /feedwater and and 2/ loop level coin-flow mismatch 2/ loop-flow flow mis-cident with mismatch match or 1/ loop-2 loop / level flow mis-and I/ loop-match in flow mis-same loop match

18. A. Reactor Trip Breakers 2

2 1

8 B. Reactor Trip 2

I I

Bypass Breakers - Note C

19. Automatic Trip Logic 2

2 1

11 Note C - With the Reactor Trip Breaker open for surveillance testing in accordance with Specification Table 4.1-1 (item 30) if PERMISSIBLE BYPASS CONDITIONS - P-6 P-7, P-8 and P-10 are defined in TS Table 4.1-A M

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),

94 N

a N

a TS 3.7-13 I

TABLE 3.7-1 (Continued)

TABLE NOTATION 7

ACTION STATEMENTS ACTION 1.

With the number of channels OPERABLE, one less than required by the minimum OPERABLE Channels requirement, restore the inoperable channel to OPERABLE status within.,8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and/or open the reactor trip breakers.

ACTION 2.A.

With the number of OPERABLE channels equal to the Minimum OPERABLE Channels, POWER OPERATION may proceed provided the following conditions are satisfied:

1.

The inoperable channel is placed it. the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

2.

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of the redunds.nt channel (s) per Specification 4.1.

3.

Either, THERMAL POWER is restricted to s75% of RATED POWER and the Power Range, Neutron Flux trip setpoint is reduced to s85% of RATED POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT POWER TILT is monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

1 i

i i

i j

Amendnent Nos, 117 and 117 1

TS 3.7-13a TABLE 3.7-1 (Continued) 4.

The QUADRANT POWER TILT shall be determined to be within the limit when above 75 percent of RATED POWER with one Power Range Channel inoperable by using the moveable incore detectors to confirm that the normalized symmetric power distribution, obtained from 2 sets of 4 symmetric thimble locations or a full-core flux map, is consistent with the indicated QUADRANT POWER TILT at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

2.B.

With the number of operable channels one less than required by the Minimum Operable channels requirement, be in Hot Shutdown within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 3.

With the number of channels OPERABLE one less than required by the Minimum OPERABLE Channels requirement and with the THERMAL POWER level:

a.

Below P-6, (Block of Source Range Reactor Trip) setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint.

b.

Above P-6, (Block of Source Range Reactor Trip) setpoint, but below 10% of RATED POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 10% of RATED POWER.

Above 10% of RATED POWER, POWER OPERATION may continue.

c.

Amendnent 1los. 117 and 117

TS 3.7-13b TABLE 3.7-1 (Continued)

ACTION 4 With the number of channels OPERABLE one less than required by the Minimum OPERABLE Channels requirement and with the. THERMAL POWER level:

a.

Below P-6, (Block of Source Range Reactor Trip) setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 setpoint.

b.

Above P-6, operation may continue.

ACTION 5.

With the number of channels OPERABLE one less than required by the Minimum OPERABLE Channels requirement, verify compliance with the SHL'TDOWN MARGIN requirements within I hour and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

ACTION 6.A.

With the number of OPERABLE Channels equal to the Minimum Operable Channels, POWER OPERATION may proceed provided the following conditions are satisfied:

1.

The inoperable channel is placed in the tripped cendition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

2.

The Minimum OPERABLE Channels requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels per Specification 4.1.

6.B.

With the number of OPERABLE Channels one less than required by the Minimum Operable Channels requirement, be in Hot Shutdown within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Amendment Nos.II7 and II7

\\

TS 3.7-13c TABLE 3.7-1 (Continued)

ACTION 7.A.

With the number of OPERABLE Channels equal to the Minimum Operable Channels, POWER OPERATION may proceed until performance of the next required CHANNEL FUNCTIONAL TEST provided the inoperable channel is placed in the tripped condition within 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

7.B.

With the number of OPERABLE Channels one less than required by the Minimum Operable Channels requirement, be in Hot Shutdown within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

J ACTION 8 A.

With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

In conditions of. operation other than REACTOR CRITICAL or POWER OPERATIONS, with the number of OPERABLE Channels one less than 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 open the reactor trip breakers within the next hour. However, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.1. provided the other channel is OPERABLE.

i ACTION 8.B.

With one of the diverse trip features (undervoltage or shunt trip device) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inoperable and apply Action 8.A.

The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for performing maintenance to restore the breaker to OPERABLE status, Amendment Hos, 117 andll7 l

i TS 3.7-13d TABLE 3.7-1 (Continued)

ACTION 9.

With one channel inoperable, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or reduce THERMAL POWER to below the P-8, (Block of Low Reactor Coolant Pump Flow and Reactor Coolant Pump Breaker Position) setpoint, within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . Operation below P-8 may continue pursuant to ACTION 10.

ACTION 10.

With less than the Minimum Number of Channels OPERABLE, operation may continue provided the inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 11.

With the number of OPE"ABLE Channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT SKUTDOWN within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

In conditions of operation other than REACTOR CRITICAL or POWER OPERATIONS, with the number of OPERABLE Channels one less than 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 open the reactor trip breakers within the next hour.

However, one channel may be bypassed for up to 2 i

hours for surveillance testing per Specification 4.1.

provided the other chtnnel is OPERABLE.

ACTION 12.

With the number of OPERABLE channels less than the total number of channels, operation may continue provided the inoperable channels are placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

)

i Amendment Nos. 117 and 117

~s

TS 4.1 -1 4.1 OPERATIONAL SAFETY REVIEk' Applicability Applies to items directly related to safety limits and limiting conditions for operation.

Objective To specify the minimum frequency and type of surveillance to be applied to unit equipnent and conditions.

Specification A.1 Calibration, testing, and checking of instrumentation channels l

shall be performed as detailed in Table 4.1-1 and 4.1-2.

(

A.2 The logic for the reactor trip system interlocks listed in Table 4.1-A shall be demonstrated operable prior to each reactor startup unless performed during the pr4ceeding 92 days.

The interlock function shall be demonstrated operable at each refueling by channel calibration testing of each channel affected by interlock operation.

B.

Equipment tests shall be conducted as detailed below and in Table 4.1-2A.

1.

Each Pressurizer PORV shall be demonstrated operable:

j a.

At least once per 31 days by performance of a channel functional test, excluding valve operation, and b.

At least once per 18 months by performance of a channel calibratio1, 2.

Each Pressurizer PORV block valve shall be demonstrated j

operable at least once per 92 days by operating the valve through one complete cycle of full travel.

Amendment t'os.117 and 117

~.

l TABLE 4.1-1 MINIMUM FREQllENCIES FOR CHECK, CALIBRATIONS AND TEST OF INSTRUMENT CilANNELS Channel Description Check Calibrate Test Remarks 1.

Nuclear Power Range S

I)( 1)

M(2)

1) Against a heat balance standard O(3)

2) Signal at AT; bistable action R(4)

(permissive, rod stop, trip)

3) Ilpper and lower chambers for symmetric offset by means of the movable incore detector system

4) Neutron detectors may be exciuded from Channel Calibration 2.

NucIcar Intermediate Range

S R(2)

P(l) 1)

I.og level; bistable action (below P-10 setpoint)

(permissive, rod stop, trip)

2) Neutron detectors may be excluded from Channel Calibration 3.

Nuclear Source Range

S R(2)

P(l) 1)

Bistable action (alarm, trip)

(below P-6 setpoint)

2) Neutron detectors may be excluded from Channel Calibration 4.

Reactor Coolant Temperature

S R

M(1)

1) Overtemperature AT M(2)

2) Overpower AT 5.

Reactor Coolant Flow S

R H

I 6.

Pressurizer Water Level S

R M

di 7.

Pressurizer Pressure (Higi & Low)

S R

H s

we v>

8.

4 kV Voltage and Frequency N.A.

R H

f' e

s, m

9.

Analog Rod Position

S(1,2)

R M(3)

1) With step counters El (4) 2)

Each six inches of rod motion 1

j when data logger is out of service

3) Rod bottom histable action 4) fl.A. when reactor is in cold shutdown.

~

TAHl.E 4.1-1 (Continued)

MINIMUM FREQtlENCIES FOR CIIECK, CAI.lBRATIONS AND TEST OF INSTRIIMENT CIIANNEl.S Channel Description Check Calibrate Test Remarks 10.

Rod Position Bank Counters S(1,2)

N.A.

1) Each six inches of rod motion when data logger is out of service

2) With analog rod position 11.

Steam Generator I.evel S

R M

12.

Charging Flow N.A.

R N.A.

13.

Residual Heat Removal Pump Flow N.A.

R N.A.

14.

Boric Acid Tank Level

D R

N.A.

15.

Refueling Water Storage Tank Level S R

M 16.

Volume Control Tank 1.evel N.A.

R N.A.

17.

Reactor Containment Pressure-CI.S

P R

M(I) 1)

Isolation valve signal and spray signal.

18.

Boric Acid Control N.A.

R N.A.

e R

19.

Containment Sump Level N.A.

R N.A.

m 3

20.

Accumulator Level and Pressure S

R N.A.

21.

Containment Pressure-Vacuum Pump S

R N.A.

g System m

22.

Steam Line Pressure S

P.

M 7

o.

~

m.______.

TAHl.E 4.1-1 (Continued)

~

4 MINIMUM FREQUENCIES FOR CHECK, CALIBRATIONS AND TEST OF INSTRUMENT CHANNELS Channel Description Check Calibrate Test Remarks 23.

Turbine First Stage Pressure S

R M

24.

Emergency Plan Radiation Instr.

M R

M s

25.

Environmental Radiation Monitors

M N.A.

N.A.

TI.D Dosimeters 26.

I.ogic Channel Testing N.A.

N.A.

M 27.

Turbine Overspeed Protection N.A.

R R

Trip Channel (Electrical) d 28.

Turbine Trip Setpoint verification is not A.

Stop valve closure N.A.

N.A.

P applicable B.

Low fluid oil pressure N.A.

N.A.

P 29.

Seismic Instrumentation M

R M

30.

Reactor Trip Breaker N.A.

N.A.

H The test shall independently verify operability of the undervoltage and shunt trip attachments

$g 31.

Reactor Coolant Pressure (Low)

N.A.

R N.A.

1 i

j

$I

{

g 32.

Auxiliary Feedwater f

[

a.

Steam Generator Water I.evel S

R M

g 3

,5*

I m -I m m

1 f'

j h.

RCP Undervoltage S

R M

4 a

l g

c.

S.I.

(All Safety Injection surveillance requirements) p i

j d.

Station Blackout N.A.

R N.A.

I c.

Main Feedwater Pump Trip N.A.

N.A.

R

TABLE 4.1-1 (Continued)

~

MINIMUM FREQUENCIES FOR CHECK, CALIBRATIONS AND TEST OF INSTRUMENT CHANNELS Channel Description Check Calibrate Test Remarks l

33.

Loss of Power a.

4.16 KV Emergency Bus Under-N.A.

R M

voltage (Loss of Voltage) b.

4.16 KV Emergency Bus Under-H.A.

R H

voltage (Degraded Voltage) l 34.

Control Room Chlorine Detectors S

R M

35.

Manual Reactor Trip N.A.

N.A.

R The test shall indepes.dently verify the operability of the undervoltage and shunt trip attachments for the manual reactor t rip function. The test shall also verify the operability of the bypass breaker trip circuit.

36.

Reactor Trip Bypass Breaker N.A.

N.A.

M(1). R(2)

(1) Local manual undervoltage trip prior to placing breaker in service.

(2) ' Automatic shunt trip.

e S

S 37.

Safety Injection input f rom ESF N.A.

N.A.

R 5

38.

Reactor Coolant Pump Breaker N.A.

N.A.

R S

Position Trip

~

a" II 39.

Steam /Feedwater Flow and low S

R H

S/G Water Level 7

ao S

- Each shift M

- Monthly 7

~}

D

- Daily P

- Prior to each startup if not done within the N.A.- Not Applicable previous week Q

- Every 90 effective full power days R

- Each Refueling Shutdown See Specification 4.1.D

- =.

l TAHI.E 4.1-A

^

REACTOR TRIP SYSTEM INTERh0CKS l

l 1

DF.SIGNATION CONDITION FUNCTION i

l P-6 I of 2 Intermediate range Allows manual block of source range reactor trip above setpoint (increasing power level) 2 of 2 Intermediate range Automatically defeats the block of source range below setpoint (decreasing reactor trip power level)

P-10 2 of 4 Power range above set-Allows manual block of power range (low setpoint) point (increasing power level) and intermediate range reactor trips and inter-mediate range rod stop.

Automatically blocks source range reactor trip.

3 of 4 Power range below set-Automatically defeats the block of power range point (decreasing power level)

(low setpoint) and intermediate range reactor trips and intermediate range rod stop.

Input to P-7.

P-7 2 of 4 Power range above setpoint Allows reactor trip on: Low flow or reactor coolant or pump breakers open in more than one loop. Undervoltage g

I of 2 Turbine Impulse chamber (RCP busses),ifnderfrequency (RCP busses), Turbine Trip, above setpoint Pressurizer low pressure, and Pressurizer high level.

gt (Power level increasing) e 5

3 of 4 Power range below setpoint Prevents reactor trip on: Low flow or reactor coolant g

and pump breakers open in more than one loop Undervoltage 2 of 2 Turbine Impulse chamber (RCP busses), Underfrequency (RCP busses), Turbine Trip, u

pressure below setpoint Pressurizer low pressure, and Pressurizer high level e

II (Power level decreasing) m s

o, o

e ci P-8 2 of 4 Power range above setpoint Permit reactor trip en low flow or reactor coolant pump (Power level increasing) breaker open in a single loop.

3 of 4 Power range below setpoint Riocks reactor trip on low flow or reactor coolant pump (Power level decreasing) breaker open in a single loop.

TARI.E 4.1-I A RADIOACTIVE LIOUID EFFI.UENT MONITORING INSTRUMENTATION Si!RVEII. LANCE REQllIREMENTS CilANNEI.

CilANNEL CllANNEI.

S0llRCE CilANNEL FUNCTIONAL DESCRIPTION CilECK CllECK CALIBRATION TEST I.

CROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE (a) Liquid Radwaste Effluent Line D

PR R

Q 2.

CROSS RETA OR CAP 9tA RADI0 ACTIVITY MONITORS PROVIDING ALARM RIIT NOT PROVIDING AUTOMATIC TERMINATION OF REI. EASE (a) Circulating Water Discharge Line D

M R

0 (b) Component Cooling Service Water System Effluent Line D

M R

Q 3.

FI.0W RATE MEASUREMENT DEVICES (a) Liquid Radwaste Effluent Line D

N.A.

R N.A.

E e

D - Daily M - Monthly o.f R - Each Refueling Shutdown to Q - Quarterly PR - Prior to each release g

y N.A. - Not Applicable M

s-a T

w*

t u

.= =-

TABI.E 4.1-1B RADI0 ACTIVE CASE 0tlS EFFLIIENT MONITORING INSTRl! MENTATION Si!RVEII,I.ANCE REQlIIREMENTS

CilANNFI, CilANNEL

CilANNEI, S0tIRCE

CilANNEI, FilNCTIONAI.

DESCRIPTION CliECK CilECK CALIBRATION TEST I.

PROCESS VENT SYSTEM (a) Noble Cas Activity Monitor Providing Alarm and Automatic Termination of Release D

M*

R Q

(b) Iodine Sampler W

N.A N.A N.A.

(c) Particulate Sampler W

N.A.

N.A N.A.

(d) Process Vent Flow Rate Monitor D

N.A.

R N.A.

(e) Sampler Flow Rate Measuring Device D

N.A.

SA N.A.

2.

WASTE CAS HOLDUP SYSTFM EXPI,0SIVE GAS MONITORING SYSTEM (a) Hydrogen Monitor D

N.A.

Q(1)

M (b) Oxygen Monitor D

N.A.

Q(2)

M 3.

CONDENSER AIR EJECTOR SYSTEM (a) Cross Activity Monitor D

M R

Q (b) Air Ejector Flow Rate Measuring Device D

N.A.

R N.A.

4.

VENTII.ATION VENT SYSTEM (a) Noble Gas Activity Monitor D

M R

Q (b) Iodine Sampler W

N.A.

g (c) Particulate Sampler W

N.A.

(d) Ventilation Vent Flow Rate Monitor D

N.A.

R N.A.

g (e) Sampler Flow Rate Measuring Device D

N.A.

SA N.A.

m 3

(1) - The channel calibration shall include the use of standard gas samples containing a nominal:

r+

g[

1.

one volume percent hydrogen, balance nitrogen, and y'

2.

four volume percent hydrogen, balance nitrogen.

I2 23 (2) - The channel calibration shall include the use of standard gas samples containing a nominal:

I 1.

one volume percent oxygen, balance nitrogen. and y

g[

2.

four volume percent oxygen, balance nitrogen.

7 o,

23 D - Daily R - Each Refueling Shutdown Q - Quarterly 7'

W - Weekly SA - Semi-annually

- Monthly and prior to each Waste Gas M - Monthly NA - Not Applicable Decay Tank Release

- --

ML20149K058

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