Text

Amend 120 to License DPR-66,incorporating Number of Changes in Areas of Instrumentation & Administrative Controls
	ML20237A781
Person / Time
Site:	Beaver Valley
Issue date:	12/07/1987
From:	Stolz J; Office of Nuclear Reactor Regulation
To:	; Duquesne Light Co, Ohio Edison Co, Pennsylvania Power & Light Co
Shared Package
ML20237A783	List: ML20237A781; ML20237A794;
References
	DPR-66-A-120 NUDOCS 8712150256
	Download: ML20237A781 (18)
	v • d • e

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o UNITED STATES

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",'g NUCLEAR REGULATORY COMMISSION g

WASHINGTON. D. C. 20555 DUQUESNE LIGHT C09ANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLEY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 120 License No. DPR-66 1.

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

A.

The application for amendment by Duquesne Light Company, Ohio Edison Company, and Pennsylvania Power Company (the licensee) j dated February 24, 1987 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 confonnity 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 amendment will not be ininical 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 2.C.(2) of Facility Operating License No. DPR-66 is hereby amended to read as follows:

[k Do$

f

2-(2) Technical Specifications I

l The Technical Specifications contained in Appendix A, I

as revised through Amendment No.120, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This amendment is effective on issuance, to be implemented no later than 30 days after issuance.

FOR THE NUCLEAR REGULATORY COMMISSION bbO

A Jo F. Stolz, Dire r

.iect Directorat

-4 vision of Reactor Projects I/II

Attachment:

Changes to the Technical Specifications Date of Issuance: December 7, 1987 i

l e

l ATTACHMENT TO LICENSE AMENDMENT NO.120 FACILITY OPERATING LICENSE NO. OPR-66 DOCKET NO. 50-334 i

l Replace the followir.g pages of the Appendix A (Technical Specifications) with the enclosed pages. The revised pages are identified by amendment number and i

l I

contain vertical lines indicating the area of change.

i Remove Insert 3/4 2-6a 3/4 2-6a 3/4 3-2 3/4 3-2 3/4 3-27 3/4 3-27 3/4 3-28 3/4 3-28 3/4 3-35 3/4 3-35 3/4 3-38 3/4 3-38 3/4 3-46 3/4 3-46 3/4 4-10d 3/4 4-10d 3/4 5-3 3/4 5-3 3/4 5-6 3/4 5-6 3/4 6-1 3/4 6-1 6-11 6-11 6-12 6-12 6-22 6-27 6-24 6-24 l

l l

1 POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued)

\\

2.

When the F C is less than or equal to the FRTP limit xfor the appropriate measured core i

pYkne, additional power distribution shall be maps F[y and C

compared to and F

taken leastonce[er31EFPD.

x F

at xy for Rated Thermal Power (FgTP shall be prbided for all core planes containing bank ")D" control e.

The F

limit rods and all unrodded core planes in a Radial Peaking Factor Limit Report per specification 6.9.1.14.

f.

The F

limits of e,

above, are not applicable in the follow 1hg plane regions as measured from the bottom of g

core the fuel:

1.

Lower core region from 0 to 15%, inclusive.

2.

Upper core region from 85 to 100%, inclusive.

3.

Grid plane regions 2%

of core height (12.88 inches) measured from grid centerline.

f 4.

Core plane regions within 12%

of core height (12.88 I

inches) about the bank demand position of the bank "D"

control rods.

L the effects of F

F [C evaluatbd xy (on exceeding F

g.

With x,

x Z) is hall be to determine if Fg Fg (Z) within its limit.

4.2.2.3 When Fo (Z) is measured pursuant to Specification 4.10.2.2, an overall measured Fg (Z) shall be obtained from a power distribution map and increased by 3% to account for manufacturing tolerances and further increased by 5% to account for measurement uncertainty.

Anendnent No. k,120 BEAVER VALLEY - UNIT 1 3/4 2-6a

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l TABLE 3.3-5 (Continued)

ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 4.

Steam Line Pressure-Low a.

Safety Injection (ECCS) 1 13.0#/23.0##

b.

Reactor Trip (from SI) 1 3.0 l

/

c.

Feedwater Isolation 1 75.0(1) d.

Conte.inment Isolation-Phase "A"

1 22.0#/33.0##

e.

Auxiliary Feedwater Pumps Not Applicable f.

Rx Plant River Water System 1 77.04/110.0##

g.

Steam Line Isolation 1 8.0 1

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5.

Containment Pressure--High-High a.

Containment Quench Spray 1 77.0 i

b.

Containment Isolation-Phase "B"

Not Applicable i

c.

Control Room Ventilation Isolation 1 22.0#/77.0##

l 6.

Steam Generator Water Level--High-High a.

Turbine Trip-Reactor Trip 1 2.5 j

(Above P-9) l b.

Feedwater Isolation 1 13.0(2) l l

l 7.

Containment Pressure--Intermediate High-High a.

Steam Line Isolation 1 8.0 i

Steamline Pressure Rate--High Negative 8.

a.

Steamline Isolation 1 8.0 9.

Loss of Power a.

4.16kv Emergency Bu's Undervoltage 1 1.3 (Loss of Voltage) b.

4.16kv and 480v Emergency Bus Under-1 95 voltage (Degraded Voltage)

BEAVER VALLEY - UNIT 1 3/4 3-27 Amendment No. h, D,120 l

1 TABLE 3.3-5 (Continued)

TABLE NOTATION i

Diesel generator starting and sequence loading delays included.

Response

time limit includes opening of valves to establish SI path and attainment of discharge pressure fer centrifugal charging pumps and Low Head Safety Injection pumps.

1 Diesel generator starting and sequence loading delays not included.

Offsite power available.

Response

time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps.

Diesel generator starting and sequence loading delays included.

Response

time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps.

(1)

Feedwater system overall response time shall include verification of valve stroke times applicable to the feedwater valves shown for penetrations 76, 77 and 78 on Table 3.6-1.

(2)

The 13.0 second response time includes 3 seconds for signal j

processing and 10 seconds for feedwater flow control valve j

stroke / closing time (see Table 3.6-1 FCV-lFW-478, 488 and 498).

j l

BEAVER VALLEY - UNIT 1 3/4 3-28 Amendment ilo. )Q,120

TABLE 3.3-6 (Continued)

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 lease 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.

l 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.

l 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 required by the Minimum Channels OPERABLE requirement, either restore the inoperable Channel (s) 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 l

monitoring the appropriate parameter (s), and b)

Return the channel to OPERABLE status within 30

days, or, explain in the next Semi-Annual Effluent Release Report why the inoperability-was not corrected in a timely manner.

ACTION 41 -

a)

With the number of Unit 1 OPERABLE channels one less than the Minimum Channels OPERABLE 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.

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 radiation monitor to OPERABLE status within 7 days or isolate the control 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.

j BEAVER VALLEY - UNIT 1 3/4 3-35 Amendment No.M.MR,120 i

INSTRUMENTATION SEISMIC INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.3 The seismic monitoring instrumentation shown in Table 3.3-7 shall be OPERABLE.

APPLIC ABILITY :

At all times.

ACTION:

i a.

With the number of OPERABLE seismic monitoring instruments less than required by Table 3.3-7, restore the inoperable instrument (s) to OPERABLE status within 30 days.

b.

With one or more seismic monitoring instruments inoperable for more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the Plans for restoring the instrument (s) to OPERABLE status.

c.

The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.3.1 Each of the above seismic monitoring instruments shall be demonstrated OPERABLE by the performance of the CHANNEL

CHECK, CHANNEL CALIBRATION and CRANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-4.

4.3.3.3.2 A

seismic event greater than or equal to 0.Olg shall be reported to the Commission within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Each of the above seismic monitoring instruments actuated during a seismic event greater than or equal to 0.Olg shall be restored to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and a

CHANNEL CALIBRATION performed within 30 days following the seismic event.

Data shall be retrieved from actuated instruments and analyzed to determine the magnitude of the vibratory ground motion.

A Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days describing l the magnitude, frequency spectrum and resultant effect upon facility features important to safety.

BEAVER VALLEY - UNIT 1 3/4 3-38 Amendment No.M. 120

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i EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS - Tava 1 350F LIMITING CONDITION FOR OPERATION 3.5.2 Two separate and independent ECCS subsystems shall be OPERABLE with each subsystem comprised of:

a.

One OPERABLE centrifugal charging pump, b.

One OPERABLE low head safety injection pump, and c.

An OPERABLE flow path capable of taking suction from the refueling water storage tank on a safety injection signal and transferring suction to the containment sump during the recirculation phase of operation.

APPLICABILITY:

MODES 1, 2 and 3.

I ACTION:

a.

With one ECCS subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

l b.

In the event the ECCS is actuated and injects water into the Reactor Coolant

System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days describing the circumstances of the l actuation and the total accumulated actuation cycles to date.

l 1

I i

l BEAVER VALLEY - UNIT 1 3/4 5-3

/Wendment No. DR,120 i

i i

4 EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS Tavg <350F LIMITING CONDITION FOR OPERATION minimum, one ECCS subsystem comprised of the following 3.5.3 As a

shall be OPERABLE:

a.

One OPERABLE centrifugal charging pump,#

b.

One OPERABLE Low Head Safety Injection Pump, and l

l l

c.

An OPERABLE flow path capable of taking suction from the l

refueling water storage tank upon being manually realigned and transferring suction to the containment sump during the recirculation phase of operation.

J APPLICABILITY:

MODE 4 l

ACTION:

a.

With no ECCS subsystem OPERABLE because of the inoperability of either the centrifugal charging pump or the flow path from the refueling water storage tank, restore at least one ECCS subsystem to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in l

COLD SHUTDOWN within the next 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months , l

l b.

In the event the ECCS is actuated and injects water into the Reactor Coolant

System, a Special Report shall be prepared I

and submitted to the Commission pursuant to specification 1

6.9.2 within 30 days describing the circumstances of the l l

actuation and the total accumulated actuation cycles to date.

SURVEILLANCE REQUIREMENTS 4.5.3.1 The ECCS subsystem shall be demonstrated OPERABLE per the applicable Surveillance Requirements of 4.5.2.

4.5.3.2 All charging pumps except the above required OPERABLE pumps, shall be demonstrated inoperable at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months whenever the temperature of one or more of the non-isolated RCS cold legs is 5

27 5'F by verifying that the control switches are placed in the PULL-TO-LOCK position and tagged.

A maximum of one centrifugal charging pump shall be OPERABLE whenever the temperature of one or more of the non-isolated RCS cold legs is 1 275*F.

BEAVER VALLEY - UNIT 1 3/4 5-6 Amendment No. 'Hi,120 w____________-________-______________________.

I 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY l

j LIMITING CONDITION FOR OPERATION l

3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour 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 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

SURVEILLANCE REQUIREMENTS l

l 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:

]

a.

At least once per 31 days by verifying that 1

1.

All penetrations

not capable of being closed by l

OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by

valves, blind

flanges, or deactivated automatic ~ valves secured in their positions, except as provided in Table 3.6-1 of Specification 3.6.3.1.

2.

All equipment hatches are closed and sealed.

b.

By verifying that each containment air lock is OPERABLE per Specification 3.6.1.3.

Except

valves, blind

flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed, or otherwise secured in the closed position.

These penetrations shall be verified closed during each COLD SEUTDOWN except that such verification need not be performed more often than once per 92 days.

BEAVER VALLEY - UNIT 1 3/4 6-1 Amendment No.120 1

1

ADMINISTRATIVE CONTROLS i

AUDITS (Continued) 1 l

6.'5.2.9 The ORC shall report to and advise the Senior vice President, Nuclear Group on those areas of responsibility specified in Section 6.5.2.7 and 6.5.2.8.

l l

RECORDS j

1 6.5.2.10 Records of ORC activities shall be prepared, approved and distributed as indicated by the following:

a.

Minutes of each ORC meeting shall be prepared for and approved by the ORC Chairman or Vice-Chairman within 14 days following each neeting.

b.

Reports of reviews encompassed by Section 6.5.2.7 above, shall he documented in the ORC meeting minutes.

c.

Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Senior Vice President, Nuclear Group and to the management positions responsible for the areas audited within 30 days after completion of the audit.

6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTA3LE EVENTS:

a.

The Commission shall be notified in accordance with 10 CFR 50.72 and/or a

report be submitted pursuant to the requirements cf Section 50.73 to 10CFR Part 50, and b.

Each REPORTABLE EVENT shall be reviewed by the OSC, and results of this review shall be submitted to the ORC.

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

a.

The facility shall be placed in at least HOT STANDBY within one (1) hour.

b.

The Safety Limit violation shall be reported to the Commission within one hour and to the Senior Manager Nuclear l Operations and to the ORC within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

BEAVER VALLEY - UNIT 1 6-11 Amendment No h, h Q,120 L _ __ __ __-_____

ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION (Continued) c.

A safety Limit Violation Report shall be prepared.

The report shall be reviewed by the on-Site Safety Committee (OSC).

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.

d.

The Safety Limit Violation Report shall be submitted to the l

Commission, the ORC and the Senior Manager, Nuclear Operations j

l l

within 30 days of the violation.

1 6.8 PROCEDURES l

i 6.8.1 Written procedures shall be established, implemented, and j

maintained covering the activities referenced below:

a.

The applicable procedures recommended in Appendix "A"

cf Regulatory Guide 1.33, Revision 2, February 1978.

b.

Refueling operations.

c.

Surveillance and test activities of safety related equipment.

d.

Security Plan implementation.

e.

Emergency Plan implementation.

f.

Fire Protection Program implementation.

g.

PROCESS CONTROL PROGRAM implementation.

l h.

OFFSITE DOSE CALCULATION MANUAL implementation.

6.8.2 Each procedure and administrative policy of 6.8.1 above and changes of intent thereto, shall be reviewed by the OSC and approved by the Plant

Manager, predesignated alternate or a predesignated Mcnager to whom the Plant Manager has assigned in writing the responsibility for review and approval of specific subjects considered by the committee, as applicable.

Changes to procedures and administrative policies of 6.8.1 above that do not receive OSC

review, such as correcting typographical

errors, reformatting procedures and other changes not affecting the purpose for which the procedure is performed shall receive an independent review by a qualified individual and approved by a

designated manager or director.

BEAVER VALLEY - UNIT 1 6-12 Amendment No, h,h 120

ADMINISTRATIVE CONTROLS The radioactive effluent release report to be submitted 60 days after January 1

of each year shall also include an assessment of radiation doses to the likely most exposed real individual from reactor releases for the previous calendar year to show conformance with 40 CFR

190, Environmental Radiation Protection Standards for Nuclear Power Operation.

Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Revision 1.

The SKYSHINE Code (available i

from Radiation Shielding Information Center, ORNL) is acceptable for

)

calculating the dose contribution from direct radiation due to N-16.

The radioactive effluent release reports shall include an assessment of radiation doses f rom the radioactive liquid and gaseous ef fluents released from the unit during each calendar quarter as outlined in i

Regulatory Guide 1.21.

In addition, the unrestricted area boundary maximum noble gas gamma air and beta air doses shall be evaluated.

The assessment of radiation doses shall be performed in accordance with the ODCM.

The radioactive effluent release reports shall also include any licensee initiated changes to the ODCM made during the 6 month period.

RADI AL PEAKING FACTOR LIMIT REPORT 6.9.1.14 The F

limit for Rated Thermal Power (F[$P) provided No the Regional Administrator of the Regional shall be Office of the

NRC, with a

copy to the Director, Nuclear Reactor Regulation, U.

S. Nuclear Regulatory Commission, Washington, DC 20555 for all core planes containing bank "D" control rods and alk unrodded core planes at least 60 days prior to cycle initial criticality.

In the event that the limit would be submit'ted at some other time during core life, it will be submitted 60 days prior to the date the limit would become effective unless otherwise

_ exempted by the Commission.

Any information needed to support FgTP Fill be by request fromtheNRCandneednotbeincludedinkhisreport.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator of the Regional Office of the NRC within the time period specified for each report.

These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:

BEAVER VALLEY - UNIT 1 6-22 MiendmentNo.14, 120

ADMINISTRATIVE CONTROLS 6.10.2 The following records shall be retained for the duration of the Facility Operating License:

1 a.

Records and drawing changes reflecting facility design modifications made to systems and equipment described in the Final Safety Analysis Report.

b.

Records of new irradiated fuel inventory, fuel transfers and assembly burnup histories, c.

Records of facility radiation and contamination surveys.

d.

Records of radiation exposure for all individuals entering radiation control areas.

e.

Records of gaseous and liquid radioactive material released to the environs.

f.

Records of transient or operational cycles for those facility components designed for a

limited number of transients or cycles.

g.

Records of training and qualification for current members of the plant staff.

h.

Records of in-service inspections performed pursuant to these Technical Specifications.

i.

Records of Quality Assurance activities required by the QA Manual.

j.

Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

k.

Records of meetings of the OSC and the ORC.

I 1.

Records of the service lives of all hydraulic and mechanical l

snubbers including the date at which the service life commences and associated installation and maintenance records.

m.

Records of analyses required by the Radiological l Environmental Monitoring Program.

BEAVER VALLEY - UNIT 1 6-24 Amendment No.120

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