Text

Amends 211 & 89 to Licenses DPR-66 & NPF-73,respectively, Revise Alarm Setpoints for Effluent Radiation & Incontainment Area Radiation Monitors Listed in TS Table 3.3-6
	ML20203B196
Person / Time
Site:	Beaver Valley
Issue date:	02/09/1998
From:	Stolz J; Office of Nuclear Reactor Regulation
To:	; Duquesne Light Co, Ohio Edison Co, Pennsylvania Power Co
Shared Package
ML20203B201	List: ML20203B196; ML20203B215;
References
	DPR-66-A-211, NPF-73-A-89 NUDOCS 9802240225
	Download: ML20203B196 (15)
	v • d • e

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a UNITED STATES j

,j NUCLEAR REGULATORY COMMISSION c

't WASHINGTON D.C. 20066 0001 R.....l DUOUESNE LIGHT COMPANY OHIO EDISON COMPANY i

PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 211 License No. DDR-66 1.

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

A.

The applications for amei.ent by Duquesne Lignt Company, et al.

(the licensee) dated November 6, 1995, as supplemented June 5, 1997, 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 Comission; 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; D.

The issuance of this nendment will not be inimical to the comon defense and security on 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 applicaole requirements have been satisfied.

9002240225 980209 PDR ADOCK 05000334 P

PDR

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. 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 Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.211, 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, to be implemented within 60 days.

FOR THE NUCLEAR REGULATORY COMMISSION r

k John.Stolz,Diredor P ject Directorate I-2 ivision of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: February 9, 1998

AU g(HENT TO LICENSE AMENDMENT NO.741 FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 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.

Remove Insert 3/4 3-34 3/4 3-34 3/4 3-34a 3/4 3-34a 3/4 3-35 3/4 3-35 3/4 3-35a 3/4 3-35a

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TABLE 3.3-6 DPR-66 RADIATION MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE MEASUREMENT I3I INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION

1. AREA MONITORS

-1 4

a. Fuel Storage Pool Area 1

(1) 5 15 mR/hr 10

- 10 mR/hr 19 l

l (RM-207)

b. Containment 3

6 i.

Purge & Exhaust 1

6 5 1.6 x 10 cpm 10 - 10 cpm 22 Isolation (RMVS 104 A & B) 4 7

ii. Area (RM-RM-219 2

1,2,3 & 4 s 1.5 x 10 R/hr 1 - 10 R/hr 36 l

A & B)

-2 3

c. Control Room Isolation 2

1,2,3,4,5I4I,6I#3 5.47 mR/hr 10

- 10 41 l

(RM-RM-218 A & B)

(in either unit) mR/hr

(

2. PROCESS MONITORS

a. Containment 6

1.

Gaseous Activity 1

1,2,3 & 4 N/A 10 - 10 cpm 20 RCS Leakage Detection (RM 215B) 6

11. Particulate Activity 1

1,2,3 & 4

!!/A 10 - 10 cpm 20 RCS Leakage Detection (RM 215A) 6

b. Fuel Storage Building 1

(2) 6 4.0 x 10 cpm 10 - 10 cpm 21 l

Gross Activity (RMVS-103 A & B)

-BEAVER VALLEY - UNIT 1 3/4 3-34 Amendment No.211 O

u

TABLE 3.3-6 (Continued)

DPR-66 RADIATION MONITORING INSTRUMENTATION-MINIMITA CHAN!iELS APPLICABLE MEASUREMENT II INSTPMMENT 9PERABLE MODES SETPOINT RANGE ACTION PROCESS MONITORS (Continued) 2.c.

Noble' Gas Effluent Monitors 1.

Supplementary Leak 1

1,2,3,&4 5 7.98 x 10 cpm.10

-10 uCi/cc(5) 36 l

2

-2 5

Collection and Release System (RM-VS-110 Ch.

l 7 E'Ch. 9) D) 2

-2 II 36 l

11. Auxiliary Building 1

1,2,3,&4 5 6.69 x 10 cpm 10

-10 uCi/cc Ventilation System (RM-VS- 09 Ch. 7 &

Ch.9)IpI

-10 uCi/cc(6)

-2 36 l

111. Process Vent System 1

1,2,3,&4 5 1.83 x 10 cpm 10 (RM-GW-O9 Ch. 7 &

Ch.9)IJI 1

~I 3

iv. Atmospheric Steat 1/SG 1,2,3,&4 5 5.0 x 10 cpm 10

-10 uci/cc 36 Valve and code Sa Relief Valve Disc.

ge (RM-MS-100 A, B,

C) 2

-1 3

v.

Auxiliary Feedwater 1

1,2,3,&4 5 6.5 x 10 cpm 10 -10 uci/cc 36 Pump Turbine Exhaust (RM-MS-101)

JEAVER VALLEY - UNIT 1

.3/4 3-34a Amendment No. 211 O

s

DPR-66 TABLE 3.3-6 (Continued)

TABLE NOTATIONS (1)

With fuel in the storage pool or building.

(2)

With Irradiated fuel in the stov. age pool.

(3)

Above background.

(4)

During movement of irradiated fuel or movement of heavy loads over spent fuel.

(5)

Nominal range for Ch. 7 and Ch.

9.

Alarm set on Ch. 7.

(6)

Nominal range for Ch. 7 and Ch.

9.

Alarm set on Ch.

9.

(7)

Other SPING-4 channels not applicable to this specification.

ACTION STATEMENTS ACTION 19 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 20 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply eith the ACTION requirements of Specification 3.4.6.1.

ACTION 21 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the applicable ACTION requirements of Specification 3.9.12 and 3.9.13.

ACTION 22 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.

ACTION 36 -

With the number of OPERABLE channels less than requirnd by the Minimum Channels OPERABLE requirement, either restore the inoperable Channel (m) to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or:

a)

Initiate the preplanned alternate method of monitoring the appropriate parameter (s), and b)

Return the channel to OPERABLE status within 30 days, or, explain in the next Annual Radioactive l

Effluent Release Report why the inoperability was not corrected in a timely manner.

ACTION 41 -

a)

With the numbe.r of Unit 1 OPERABLE channels one less than the Minimum Channels OPERABLF requirement:

1.

Verify the respective Unit 2 control room radiation monitor train is OPERABLE within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 31 days.

BEAVER VALLEY - UNIT 1 3/4 3-35 Amendment No. 211

' -. ~ '

DPR-66 T23LE 3.3-6 fContinued)

ACTION STATEMENTS ACTION 41 (Continued) 2.

With the respective Unit 2

control room radiation monitor train inoperable, suspend all operations involving movement of irradiated fuel within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and restore the Unit 1

control room raitation monitor to l

OPERABLE status within 7,

.,s or isolate the l

control room from the outside atmosphere by closing all series air intake and exhaust t

isolation-dampers, unless ~the respective Unit 2 control room radiation monitor train is restored to OPERABLE status within 7 days.

b)

With no Unit-1 control room radiation monitors OPERABLE:

1.

Verify both Unit 2 control room radiation monitors are OPERABLE within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at 1 east once per 31 days.

2.

With either Unit 2 control room radiation onitor inoperable, suspend all operations

_volving movement of irradiated _ fuel within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and restore the respective Unit 1 control room radiation monitor train-to OSFRABLE status within 7 days or isolate the cc.4 trol room from the outside-. atmosphere by closing _ all series air intake and exhaust isolation

dampers, unless the respective Unit 2 control room radiation monitor train is restored to OPERABLE status within 7 days.

3.

With nc Unit 2

control-room radiation monitors OPERABLE, immediately isolate the combined control room by closing all series air-intake and exhaust isolation dampers and 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 .

BEAVER VALLEY - UNIT 1 3/4 3-35a Amendment No.211

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k UNITED STATES g

j NUCLEAR REGULATORY COMMISSION

~ 1" WASHINGTON, D.C. 20666-0001

$4.....,o DUOVESNE LIGHT COMPANY OHIO EDISON COMPANY THE CLEVELAND ELECTRIC ILLUMINATING COMPANY THE TOLEDO EDISON COMPANY DOCKET NO. 50-412 BEAVER VALLEY POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 89 License No. NPF-73 1.

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

A.

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

(the licensee) dated November 6, 1995, and March 11, 1996, as supplemented June 5, 1997, 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 conformity with the application',

the provisions of the Act, and the rules and regulations of the 1

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 Commission's regulations; D.

The issuance of this amendment will not be in;uical 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 Pan-t 51 of the Comission's regulations and all applicable requirements have been satisfied.

. 2.

Accordingly, the license is amendet by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facilin,y Operating License No. NPF-73 is hereby amended to read as follows:

(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 89. and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license. DLCO shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

't.

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

FOR THE NUCLEAR REGULATORY COMMISSION o

F. Stolz, Direc oject Directorate 1-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: February 9, 1998 4

_a

ATTACHMENT TO LICENSE AMENDMENT N0. 89 FACILITY OPERATING LICENSE NO. NPF-73 DOCKET NO. 50-412 Replace the following pages of Appendix A, Technical Specifications, with the enclosed pages as indicated. The revised pages are identified by amendnent number and contain vertical lines indicating the areas of change.

Remove Insert 3/4 3-40 3/4 3-40 3/4 3-41 3/4 3-41 3/4 3-42 3/4 3-42 3/4 3-42a e

s-

.u.

i TABLE 3.3-6 RADIATION MONITORING INSTRUMENTA* R MINIMUM CHANNELS APPLICABLE MEASUREMENT I3I INSTRUMENT OPERABLE MODES SETPOINT RAl*3E ACTION l

1. AREA MONITORS

a. Fuel Storage Pool Area 1

(1)

$75.8 mR/hr 10-Ito 10 mR/hr 19 l

4 (2RMF-RQ202) 4 7

b. Containment Area 2

1,2,3 &4

$2.0x10 R/hr 1 to 10 R/hr 36 l

(2RMR-RQ206 & 207)

c. Control Room Area 2

1 2,3 &4

$0.476 mR/hr 10-2to 10 mR/hr 46,47 3

II l

(2RMC-RQ201 & 202)

S

&6

2. PROCESS MONITORS

a. Containment i.

Gaseous Activity (Xe-133) 1 1,2,3 &4 N/A 10-6to 10-IgC1/cc 20 RCS Leakage Detection (2RMR-RQ303B) ii. Particulate Activity (I-131) 1 1,2,3 & 4 N/A 10-10to 10 gCi/cc 20

-5 RCS Leakage Detection (2RMR-RQ303A)

b. Fuel Building Vent i.

Gaseous Activity (ve-133) 1 (2) 57.82x10-6 Ci/cc 10-6to 10 gCi/cc 21 l

-I (2PMF-RQ301B)

BEAVER VALLEY - UNIT 2 3/4 3-40 Amendment No. 89

w__..._.

NPF-73 l

TABLE 3.3-6 (Continued)

RADIATION MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE MEASUREMENT INSTRUMENT OPERABLE MODES SETPOINTI3I RANGE ACTION

2. PROCESS MONITORS (Continued)

11. Particulate (I-131) 1 (2).

56.70x10-9pCi/cc 10-10to 10-5pC1/cc-21 l

(2RMF-RQ301A)

c. Noble Gas and Effluent Monitors 1.

Supplementary Leak Collection and Release System 2

1)

Mid Range Noble Gas 1

1,2,3&4 N.A.

10-4to 10 pC1/cc.

36 (Xe-133) (2HVS-RQ109C) 2)

High Range Noble Gas 1

1,2,3&4 N.A.

10-Ito 10 pci/cc 36 5

(Xe-133) (2HVS-RQ109D)

11. Containment Purge Exhaust 1

6

$1.01x10-3pci/cc 10-sto 10-IgC1/cc 22 l

(Xe-133) (2HVR-RQ104A & B) 3 111. Main Steam Discharge 1/SG 1,2,3&4 $3. 9x10-2pci/cc 10-2to 10 pCi/cc 36 (Kr-88) (2 MSS-RQ101A,B & C) l BEAVER VALLEY - UNIT 2 3/4 3-41 Amendment No. 89

NPF-73 i'

l TABLE 3.3-6 (Continued)

TABLE NOTATIONS (1)

With fuel in the storage pool or building.

(2)

With irradiated fuel in the storage pool.

(3)

Above background.

(4)

During movement of irradiated fuel.

ACIION STATEMENTS

(

ACTION 19 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE n

requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

]"

ACTION 20 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1.

ACTION 21 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the applicable ACTION requirements of Specifications 3.9.12 and 3.9.13.

ACTION 22 - Witn the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.

ACTION 36 - With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, either restore the inoperable i

channel (s) to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or:

1)

Initiate the preplanned alternate method of monitoring the appropriate parameter (s), and 2)

Return the channel to OPERABLE status within 30 days, or, explain in the next Annual Radioactive l

Effluant Release Report why the inoperability was not corrected in a timely manner.

-L_

-mB J

BEAVER VALLEY - UNIT 2 3/4 3-42 Amendment No. 89 E

....i -..

NPF-73 6

TABLE 3.3-6 (Continued)

ACTION STATEMENTS (Continued)

ACTION 46 - With the number of OPERABLE channels one less than required by the Minimum Channels OPERABLE requirement, either restore the inoperable channel to OPERABLE status within 7

days or close the control room series norac1 air intake and exhaust isolation dampers.

ACTION 47 - hith no CPERABLE channels either restore one inoperable channel to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or close the control room series normal air intake and exhaust isolation dampero.

(

BEAVER VALLEY - UND 2 3/4 3-42a Amendment No. gg l

l a

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ML20203B196

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