ML20154P772

From kanterella
Jump to navigation Jump to search
Amends 130 & 6 to Licenses DPR-66 & NPF-73,respectively, Clarifying Surveillance Frequency of Safety Injection Input to Reactor Trip Sys & Deleting Backup Initiating Signal for Auxiliary Feedwater Sys
ML20154P772
Person / Time
Site: Beaver Valley
Issue date: 09/23/1988
From: Stolz J
Office of Nuclear Reactor Regulation
To:
Duquesne Light Co, Ohio Edison Co, Pennsylvania Power Co
Shared Package
ML20154P775 List:
References
DPR-66-A-130, NPF-73-A-006 NUDOCS 8810030177
Download: ML20154P772 (18)
v • d • e


Text

.

  1. c3 cen

~%,

UNITED STATES NUCLEAR REGULATORY COMMISSION o.

{

,I wAssimoToN, o. c. roess

\\,...../

DUQUESNE LIGHT C0!4PANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY 00CVET NO. 50-334 BEAVER VALLEY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 130 License No. OPR-66 1.

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

A.

The application for amendment by Duquesne Light Company, et al.

(thelicensee)datedJune 27, 1988, complies with the standards and requirerents 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; S.

The faci *ity will o)erate in conformity with the application, the provisions of tie Act, and the rules and regulationc of the Comission; C.

Thers 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, gjoogDocno500o334 ol77 000923 p

PNU e

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. DPR-66 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 130, are hereby incorporated in the licenso.

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

3.

This license amendment is effective on issuance, to be implemented within 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION O

[JohbF.Stolz, Director i roject Directorate I-4 L/

D division of Reactor Projects 1/11 Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance:,$EP33tges 6

ATTACHMENT TO LICENSE AMENDMENT NO.130 FACILITY OPERATING LICENSE N0. DPR-66 DOCKET NO. 50-334 Replace the following pages of Appendix A (Technical Specifications) with the enclosed pages as indicated.

"...e revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove Insert 3/4 3-12 3/4 3-12 3/4 3-13 3/4 3-13 3/4 3-19a 3/4 3-19a 3/4 3-24a 3/4 3-24a 3/4 3-27a 3/4 3-27a 3/4 3-31a 3/4 3-31a 3/4 4-2d 3/4 4-2d I

1 4

i

TABLE 4e3-1, (CONTINUED) a g

REACTOR TRIP SYSTES _ INSTRUMENTATION SURVEILLANCE REQUIREMENTS M*

Channel Modes in which.

Channel Channel Functional Surveillance Functional Unit Check Calibration Test Required ta E 15.

Steam Feedwater Flow Mis-S R

M match and Low Steam Gen-1, 2 e

erator Water Level C$ 16.

Undervoltage-Reactor N.A.

R M

1 H

Coolant Pumps w

17.

Underfrequency-Reactor N.A R

M 1

Coolant Pumps 18.

Turbine Trip a.

Auto Stop Oil Pressure N.A.

N.A.

S/U(1) 1, 2

-T b.

Turbine Stop Valve N.A N.A.

S/U(1) 1, 2 Closure

/ 19.

Safety Injection Input from N.A N.A.

R ESF 1, 2 I

20.

Reactor Coolant Pump N.A N.A.

R N.A Breaker Position Trip 21.

Reactor Trip Breaker N.A.

N.A.

M(5, 11) 1, 2, 3*,

g and S/U(1) 4*,

5*

k22.

Automatic Trip Logic N.A.

N.A.

M(5) 1, 2, 3 *,

A 4*,

5*

23.

g Reactor Trip System Interlocks A.

P-6 N.A.

N.A.

M(9) 1, 2 B.

P-8 N.A.

N.A.

M(9) 1

_f C.

P-9 N.A.

N.A.

M(9) 1 E

D.

P-10 N.A.

N.A.

M(9) 1 E.

P-13 N.A.

R M(9) 1 C

24.

Reactor Trip Bypass N.A.

N.A.

M(12), R(13),

1, 2,

3*

Breakers S/U(1) 4*,

5*

TABLE 4.3-1 (CONTINUED)

NOT(IJON With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.

(1)

If not performed in previous 7 days.

(2)

Heat balance only, above 15% of RATED THERMAL POWER.

(3)

Compare incere to excore axial imbalance above 15% of RATED THERMAL POWER.

Recalibrate if absolute difference 1 3 percent.

(4)

(Not Used) l Each train tested every other month.

(5)

(6)

Neutron detectors may be excluded from CHANNEL CALIBRATION.

(7)

Below P-10.

(8)

Below P-6.

(9)

Required only when below Interlock Trip Setpoint.

(10)

The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip circuits for the Manual Reactor Trip Function.

The test shall also verify the OPERABILITY of the Bypass Breaker trip circuit (s).

(11)

The CHANNEL FUNCTIONAL TEST chall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers.

4 (12)

Local manual shunt trip prior to placing breaker in service.

1 l

(13)

Automatic undervoltage trip.

t i

BEAVER VALLEY - UNIT 1 3/4 3-13 Miendment No.14. 'MQ,130

a, TABLE 3.3-3 (Continued)

Q Q

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION E

MINIMUM M

TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABI.E MODES ACTION i

C b 7.

AUXILIARY FEEDWATER e

a.

Steam Gen. Water Level-Low-Low (Loop Stop Valves Open) 1.

Start Turbine Driven Pump 3/stm. gen.

2/stm. gen.

2/stm. gen.

1, 2, 3 14 any stm. gen.

w1-11.

Start Motor Driven Pumps 3/sta. gen.

2/stm. gen.

2/stm. gen.

1, 2, 3 14 y

4 any 2 stm. gen.

any 2 stm. gen.

E b.

Undervoltage-RCP (Start Turbine Driven Pump (3)-1/ bus 2

2 1

14 c.

S.I.

(Start Motor-Driven Pumps)

See 1 above (all S.I.

initiating functions and requirements)

N E

d.

Baergency Bus Under-voltage (Start Motor 1/ bus 1

1 1, 2, 3

18 S

Driven Pumps)

E e.

Trip of Main Feedwater I

Pumps - (Start Motor

~

Driven Pumps) 1/ pump 1

1 1,

2, 3

18 l

_= _

l to g

TABLE 3.3-4 (Continued) cc M

W ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS t*

C'

.M FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES l

c I

z l

l 7.

AUXILIARY FEEDWATER

-a.

Steam Generator Water Level-low-low 1 12% of narrow range 2 111, of narrow range instrument span each instrument span each steam generator steam generator wg b.

Undervoltage - RCP 2 2750 volts RCP bus 2 2725 volts RCP bus voltage voltage w

I M

I c.

S.I.

See 1 above (all SI Setpoints) d.

Emergency Bus Undervoltage 5 3350 volts 1 3325 volts e.

Trip of Main Feedwater Not Applicable Not Applicable l

Ptamps t

P i

e l

l N

TABLE 3.3-5 (Continued)

ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND, FUNCTION RESPONSE TIME IN SECONDS

11. Steam Generator Water Level-Low-Low a.

Motor-driven Auxiliary 60.0 Feedwater Pumps **

b.

Turbine-driven Auxiliary 60.0 Feedwater Pumps ***

12. Undervoltage RCP a.

Turbine-driven Auxiliary 60.0 Feedwater Pumps

13. Emerooney Bus Undervoltace a.

Motor-driven Auxiliary 60.0 Feedwater Pumps

14. Trip of Main Feedwater Pumps a.

Motor-driven Auxiliary 60.0 Feedwater Pumps NOTE:

Response time for Motor-driven Auxiliary 60.0 Feedwater Pumps on all S.I.

signal starts

    • on 2/3 in 2/3 Steam Generators BEAVER VALLEY - UNIT 1 3/4 3-27A Amendment No.19,130

en TABLE 4.3-2 (CONTINUED) 5<

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION M:o Channel Modes in which E

Channel Channel Functional Surveillance Q

Functional Unit Check Calibration Test Require:d 7.

AUXILIARY FEEDWATER Cz H

a.

Steam Generator Water Level-Low-Low S

R M

1, 2, 3 e

b.

Undervoltage - RCP S

R M

1, 2

c.

S.I.

See 1 above (all SI surveillance requirements)

U

^

d.

Emergency Bus N/A R

R 1,

2, 3

Y Undervoltage U

D e.

Trip of Main Feedwater Pumps N/A N/A R

1, 2, 3 1

Y 3

i R

l 3

E.

o

REACTOR C OLANT SYSTEM SURVEILLANCE REQUIREMENTS 4

4.4.1.3.1 The required residual heat removal loop (s) shall be determined OPERABLE per Specification 4.0.5.

l 4.4.1.3.2 The required reactor coolant pump (s), if not in operation, shall be determined to be OPERABLE once per 7 days be verifying correct breaker alignments and indicated power availability.

4.4.1.3.3 The required steam generator (s) shall be determined OPERABLE by verifying secondary side level equivalent to 12% narrow range at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

4.4.1.3.4 At least one coolant loop shall be verified to be in opcration and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

i i

BEAVER VALLEY - UNIT 1 3/4 4-2d Amemiment No. 44,130

Sa Cig

/

e, '

UNITED STATES t.

NUCLEAR REGULATORY COMMISSION

{'

l WASm NGTON, D. C. 20655

\\,..../

DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY THE CLEVELAND ELECTRIC ILLUMINATING C0fiPANY THE TOLEDO EDISON COMPANY DOCKET NO. 50-412 BEAVER VALLEY POWER STATION, UNIT NO. 2 AltEP.DMENT TO FAClllTY OPERATING LICENSE Amendment No. 6 License No. NPF-73 1.

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

A.

The application for atendment by Duquesne Light Company, et al.

(the licensee) dated June 27, 1988, complies 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 f acility will operate in conformity 4 'th the application, the provisions of the Act, and the rules and regulations of the Comission; C.

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

The issuance of this amendrent will net be inimical to the comen defense and security or to the health and safety of the public; and j

E.

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

4

7.

Accordingly, the licerise is arended by changes to the Technical Specifications is indicated in the attachrent to this license amendment, and paragraph ?.C.(2) of Facility Operating License No. NFF-73 is hereby amended to read as follows:

(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 6, and the Environmental Protection Plan contained in Appendix B. both of which are attached hereto are hereby incorporated in the license.

The licensee shall operate the facility in accordanie with the Technical Specifications and the Envic;nnental Protection Plan.

3.

This license amendtrent is effective as of the date of its issuance, to be implerented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMPISSION fO, y

w ohn F. Stolz, Director Project Directorate I-4 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation At tachinent:

Changes to the Technical Specifications Date of Issuance: SEP 13 1933 h

U.

ATTACHMENT TO LICENSE AMEN 0 MENT NO. 6 i

FACILITY OPERATING LICENSE NO. NPF-73 t

DOCKET NO. 50-412 i

Replace the following pages of Appendix A (Technical Specifications) with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change, t

Remove Insert 3/4 3-20 3/4 3-20 3/4 3-27 3/4 3-27 3/4 3-31 3/4 3-31 3/4 3-37 3/4 3-37 j

3/4 4-4 3/4 4-4 l

l h

i i

i i

t l

l l

TABLE 3.3-3 (Continued) 9g EEINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION J

m MININUM N

TOTAL NO.

CHANNELS CHANNELS APPLICABLE h

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 7.

AUXILIARY FEEDWATER (Continued) z Z

d.

Safety Injection (Start See 1 above (all SI initiating functions and requirements)

Motor-Driven Pumps)

~

e.

Trip of h in Feedwater 1/ ptap 2

2 1,2,3 18 l

Pumps (Start Motor Driven Pumps) 8.

EEINEERED SAFETY FEATURE INTERLOCKS s*

a.

Reactor Trip, 2

1 2

1,2,3 45 P-4 o

b.

Pressurizer Pressure, 3

2 2

1,2,3 38 P-11 Low-Low T,yg, M 2 3

2 2

1,2,3 M

c.

1 l

l Ea2 0

(

TABLE 3.3-4 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS TOTAL SENSOR TRIP f

FUNCTIONAL UNIT ALLOWANCE (TM Z

DRIFT (S)

SETPOINT ALLOWABLE VALUE m

}

7.

AUXILIARY FEEDWATER (Continued)

E b.

Steam Generator Water Z

Level--Low-Low m

1.

Start Turbine 11.5 10.18 1.67

> 11.5% of

> 10.7% of Driven Pump Harrow range Harrow range instrument instrument span span 2.

Start Motor 11.5 10.18 1.67

> 11.5% of

> 10.7% of R

Driven Pumps harrow range Harrow range

{

instrument instrument 4

span span u

c.

Undervoltage - RCP (Start 27.7 1.39 0.0

> 75% of nominal > 73% of nominal Turbine Driven Pump) bus voltage bus voltage d.

Safety Injection See Item 1. above for all Safety Injection Trip Setpoints (Start Motor-Driven Pumps) and Allowable Values.

e.

Trip of Main Feedwater N.A.

N.A.

N.A.

M.A.

N.A.

Pumps (Start Motor-Driven Pumps) a l

?.

E l

l

.~.

l TABLE 3.3-5 (Continued)

ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 9.

Less of Power a.

4.16kv Emergency Bus Undervoltage 1 1 0.1 sec.

(Loss of Voltage) (Trip Feeder) 6.

4.16ky and 480v Emergency Bus Under-90 1 5 sec.

voltage (Oegraded Voltage) i

10. (Intentionally blank)
11. Steam Generator Water Level-Low-Low a.

Motor-driven Auxiliary

< 60.0

~

Feedwater Pump **

b.

Turbine-driven Auxiliary

< 60.0

~

Feedwater Pump ***

12. Undervoltage RCP a.

Turbine-driven Auxiliary

< 60.0

~

Feedwater Pump

13. Trip of Main Feedwater Pumps i

a.

Motor-driven Auxiliary

< 60.0 Feedwater Pumps

14. Control Room High Radistion a.

Control Room Ventilation Isolation

< 180(6) i t

l

TABLE 4.3-2 (Continued) 9 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUNENTATION SURVEILLANCE REQUIREE NTS N

p CHANNEL MODES IN )AtICH Q

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED 7.

AUXILIARY FEEDWATER (continued) d.

Safety Injection (Start Motor-See 1 above (all SI surveillance requirements)

Driven Pumps) e.

Trip of Main M.A.

N.A.

1, 2, 3 Feedwater Pumps (Start Motor-Driven Pumps) 8.

ENGINEERED SAFETY FEATURE INTERLOCKS a.

Reactor Trip, P-4 N.A.

N.A.

R 1, 2, 3 b.

Pressurizer Pressure, P-11 N.A.

R M

1,2,3 Low-Low T,,g, P-12 N.A.

R H

1, 2, 3 c.

5 i

.O

l REACTOR COOLANT SYSTEM i

i r

SURVEILLANCE REQUIREMENTS 4.4.1.3.1 The required residual heat removal loop (s) shall be determined OPERABLF per Specification 4.0.5.

4.4.1.3.2 The required reactor coolant pump (s), if not in operation, shall be determined to be OPERABLE once per 7 days by verifying correct breaker align-ments and indicated power availability.

4.4.1.3.3 The required steam generator (s) shall be determined OPERABLE by verifying secondary side level greater than or equal to 15.5 percent narrow

(

range at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

4.4.1.3.4 At least one coolant loop shall be verified to be in operation and circulating reactor ecolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, r

1 L

j P

i i

I F

i I

i l

I i

1 i

I j

J l

4 I

4 l

i i

BEAVER VALLEY UNIT 2 3/4 4 4 Amendment No. 6 l

l t

i 1

.

Retrieved from "https://kanterella.com/w/index.php?title=ML20154P772&oldid=4134823"