ML20114B916

From kanterella
Jump to navigation Jump to search
Amends 56 & 21 to Licenses NPF-39 & NPF-85,respectively, Revising TS Re Channel Calibr for Peak Acceleration Seismic Monitoring Recorder Mounted on Reactor Vessel Head Flange from 18 to 24 Months
ML20114B916
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 08/20/1992
From: Chris Miller
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20114B917 List:
References
NUDOCS 9208310357
Download: ML20114B916 (14)
v • d • e


Text

_. _

a g h% Riou

['

'n UNITED STATES 5

A

<l' !

~i NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20%$

o,s...../

PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-352 LIMERICK GENERATING STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 56 License No. NPF-39 1.

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

A.

The application 'or amendment by Philadelphia Electric Company (the licensee) dated May 8, 1991, as supplemented by letter dated May 15, 1992, 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 Commission; C.

There is reasor, ale assurance (i) that tha activities authorized by this amendment can be conducted without eidangering 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 ne 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 ar.cordance with 10 CFR Part 51 of the Commission'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, had paragraph 2.C.(2) of Facility Operating License No. NPF-39 is hereby amended to read as follous:

9208310357 920820 PDR ADOCK 05000352 P

PDR

' Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protaction Plan contained in Appendix B, as revised through Amendment No.36

, are hareby incorporated into this license.

Philadelphia Electric Company shall operate the facility in a:cordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance and is to be implemented within 30 days of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION r~

fx&k h

fvV Charles L. Miller, Director Project Directorate I-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: August 20, 199?

t

___._-_m____-_

m____

4 ATTACHMENT TO LICENSE AMENDMENT NO. y fA(,IllTY OPERATING LICENSF NO. NPF-39 QOCKET NO. 50-352 Replace the following pages of the Appendix A Technical Specifications with the attached pages.

The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

Overleaf pages are provided to maintain document completeness.*

Bam_p.yf infari 3/4 3-71 3/4 3-71*

3/4 3-72 3/4 3-72 3/4 4-7 3/4 4-7 3/4 4-8 3/4 4-8*

i r

  • )

e H -

A e

TABLE 4.3.7.2-1 SE!5MIC HON]TORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNCL CHANNEL FUNCTIONAL CHANNEL INSTRUMENTS AND. SENSOR LOCATIONS CHECK TEST CALIBRATION 1.

Triaxial Time-tilstory Accelerographs (T/A's) a.

Sensors

1) XE-VA-102 Primary Contain-N.A.

SA R

ment Foundation (Loc. 109-R16-177)

2) XE-VA-103 Containment N. A.

SA R

Structure (Diaphragm Slab)

3) XE-VA-104 Reactor Enclosure N.A.

SA R

Foundation (Loc. 111 R11-177) l

4) XE-VA-10$ Reactor Piping N.A.

SA R

Support (Mn Sim. Line 'D '

El 313', in containment),

5) XE-VA-106 Outside Contain-N. k.

SA R

ment on Seismic Category I Equipment, (RHR Heat Exchanger, Loc. 102-R15 177)

6) XRSH-VA-107* Foundation of N.A.

SA R

an Independent Seismic Category I Structure (Spray i

Pond Pump House, El 237')

b.

Recorders (Panel 00C693) 1)

XR-VA-102 for XE-VA-102 N. A.

SA R

2)

XR-VA-103 for XE-VA-103 N. A.

SA R

3)

XR VA-104 for XE-VA 104 N. A.

SA R

4)

XR-VA-105 for XE-VA-105 N.A.

SA R

S)

XR-VA-106 for XE-VA-106 N.A.

.SA R

  • Includes sensor, trigger, recorder, and backup power supply.

LIMERICK - UNIT 1 3/4 3-71 Amendment No. 40 l

MAY 3 o 1990

.1;v.,

~

~

.. OLE 4.3.7.2-1 (Continued)

SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CiiANNEL CHANNEL FUNCTIONAL CHANNEL INSTRUMENTS AND SENSOR LOCATIONS CHECK TEST CAllBRATION c.

Triaxial Seismic Trigger (S/T)

1) XSH-VA-001 (Activates N.A.

S t.

R ltems 1.b.1) thru 5) above) 2.

Triaxial Peak Recording Accelcrograph (P/A's) a.

XR-VA-151 Reactor Equipment N.A.

N.A.

l (Top of reactor vessel head) b.

XR-VA-152 Reactor Piping N.A.

N.A.

R (Mn. Stm. Line

'0,' El 313',

in containment) c.

XR-VA-153 Reactor Equipment N.A.

N.A.

R Outside Containment (RHR Heat Exchanger, Loc. 203-R15-201) 3.

Triaxial Seirmic Switches e

a.

XSHH VA-001 Primary Containment N.A.

SA R

Foundation (Loc. Il8-R16-177) 4.

Triaxial Response Spectrum Analyzer N.A.

SA R

(RSA)

  • The calibration frequency for this instrument is once per 24 months.

LIMERICK - UNIT 1 3/4 3-72 Amendment No. 40. 56

. g an. :

I

!' 3/4.4.2_ SAFETY /REL..,__

LIMITING CONDITION FOR OPERATION 3.4.2 The safety valve funciion of at least 11 of the following reactor coolant system safety / relief valves shall be OPERABLE with the specified code safety volve function lift settings:*#

4 safety / relief valves 0 1130 psig 1 %

1 5 safety / relief valves 0 1140 psig 11%

5 safety / relief valves 0 1150 psig 11%

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

With the safety valve function of one or more of the above' required a.

safety / relief valves inoperable, be in at least HOT SHUT 0GWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.

Withoneormoresafety/reliefvalvesstuckopeg,providedthatsuppression pool average water temperature is less than 105 F, close the stuck open safety /reliefvalve(s);ifunabletoclosethestuckopenvalvefs)within2 minutes or if suppression pool average water temperature is 110 F or greater, place the reactor mode switch in the Shutdown position.

With one or more safety / relief valve acoustic monitors inoperable, restore the c.

inoperable acoustic monitors to OPERABLE status within 7 days or be in at least HOT SHUTDOWrt within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVElLLANCE REQUIREMENTS 4.4.2.1 Ine acoustic monitor for each safety / relief va',ve shall be demonstrated OPERABLE with the setpoint verified to be 0.20 of the full open noise level ## by performance of a:

CHANNEL FUNCTIONAL TEST at least once per 31 days, and a a.

b.

CHANNEL CALIBRATION at least once per 18 months **.

4.4.2.0 At least 1/2 of the safety relief valves shall be removed, set pressure tested and reinstalled or replaced with spares that have been previously set pressure tested and stored in accordance with manufacturer's recommendations at least once per 24 months, and l

they shall be rotated such that all 14 cafety relief seJas are removed, set pressure tested and reinstalled or replaced with spares that :.:v" been fareviously set pressure tested and stored in accordance with manufacturer's recommendations at least once per 54 l

months.

The lift setting pressure shall correspond to ambient conditions of the valves at nominal operating temperatures and pressures.

The provisions of Specification 4.0.4 are-not applicable provided the Surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure is adequate to perform the test.

Up to 2 inoperable va'ves may be replaced with spare OPERABLE valves with lower setooints until the next refueling.

Initial settir, shall be in accordance with the manufacturer's recommendation.

Adjustrant to the valve full open noise level shall be accomplished during the startup test program.

LIMERICK - UN!1 1 3/4 4-7 Amendment No. 56

REACTOR COOLANT SYSTEM 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.3.1 The fo. lowing reactor enolant sy.

i leakage detection systems shall be OPERABLE:

The primary containment atmosphere gaseous radioactivity monitoring a.

system, b.

The drywell floor drain sump and drywell equipment drain tank flow monitoring system, c.

The drywell unit coolers condensate flow rate monitoring system, a J d.

The prir-y containment

,ure and temperature monitoring system.

APPLICABILITY:

OrtRATIONAL COND.: AuNS 1, 2 and 3.*

ACTION:

With only three of the above required leakage detection systems OPERABLE, operation may continue for up to 30 days provided grab samples of the contain-ment atmosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the required gaseous radioactive monitoring system, primary containment pressure and temperature monitoring system and/or the drywell unit coolers condensate flow rate monitoring system is inoperable; otherwise, 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 /> and in COLD SHUTOOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.4.3.1 The reactor coolant system leakage detection systems shall be demanstrated OPERABLE by:

Primary containment atmosphere gaseous radioactivity monitoring a.

systems performance of a CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months.

b.

The primary containment pressure shall be monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and the primary containment temperature shall be monitored at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c.

Drywell floor drain sump and Drywell equipment drain tank flow monitor-ing system-performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION TEST at least once per 18 months.

d.

Drywell unit coolers condensate flow rate monitoring system-performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months.

t

LIMERICK - UNIT 1 3/4 4-8

T pS RICg N

f

  • +

4' '

UNITED STATES E

I$g E

NUCLEAR REGULATORY COMMISSION o,

WASHINoTON. D.C. 20%3 g,... + /

PA1LASELPHIA ELECTRIC COMPANY DOCKET NO. 50-351 LIMERICK GENERATING STATION. UNIT 2 AMENDMENT TO FACIllTY OPERATING LICENSE Amendment % 21 License No. NPF-85 1.

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

A.

The applicatien for amendment by Philadelphia Electric Company (the licensee) dated May 8, 1991, as supplemented by letter dated May 15, 1992, 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 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.

t 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 racility Operating License No. NPF-85 is hereby amended to read as follows:

i

~

1 Technical Specifications The Techni' Specifications contained in Appendix A and the Environmental Protecticn Plan contained in Appendix B, as revised through Amendment No. 21 are hereby incorporated into this license.

Philadelphia l

Electric Company shall operate the faci'iity in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance and is to be implemented within 30 days of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION lJ j

Charles L. Miller, Director Project Directorate 1-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issitance: August 20, 1992 l

v-

-,--------,-e.r

~+~----,--,e p

ATTACHMENT TO LICENSE AMENDMENT NO. 21

)

FACILITY OPERATING LICENSE NO. NPF-85

{ LOCKET NO. 50-353 i

1 Replace the following pages of the Appendix A Technical Specifications with the attached pages.

The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

Ov#r'eaf pages are provided to maintain document completeness.*

i Remove Insert 1

3/4 3-71 3/4 3-71*-

3/4 3-72 3/4 3-72 i'

3/4 4-7 3/4 4-7 3/4 4-8 3/4 4-8*

a

!l e

i l

s l

d l

a l

a i

I

- - ~.

., ~.. -.

TABLE 4.3.7._2-1 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL FUNCTIONAL CHANNEL INSTRUMENTS AND SENSOR LOCATIONS CHECK TEST CALIBRATION 1.

Triaxial Time-History Accelerographs (T/A's) a.

Sensors

1) XE-VA-102 Primary Contain-M. A.

SA R

ment Foundation (Loc. 109-R15-177)

2) XE-VA-103 Containment N. A.

SA R

Structure (Diaphragm Slab)

3) XE-VA-104 Reactor Enclosure N.A.

SA R

Foundation (Loc. 111-R11-177)

4) XE-VA-105 Reactor Piping N.A.

SA R

Support (Mn. Stm Line 'D,'

El 313', in containment)

5) XE-VA-106 Outside Contain-N.A.

SA R

ment on ' Seismic Category I Equipme'nt, (RHR Heat Exchanger, Loc. 102-R15-177)

6) XRSH-VA-107* Foundation of N.A.

SA R

an Independent Seismic Category I Structure (Spray Pond Pump House, El 237')

b.

Recorders (Panel 000693) 1)

XR-VA-102 for XE-VA-102 H.A.

SA R

2)

XR-VA-103 for XE-VA-103 H. A.

SA R

3)

XR-VA-104 for XE-VA-104 N.A.

SA R

4)

XR-VA-105 for XE-VA-105

'N.A.

SA R

5)

XR-VA-106 for XE-VA-106 N. A.

SA R

  • Includes sensor, trigger, recorder, and backup power supply.

~

LIMERICK - UNIT 2 3/4 3-71

_______d

o TABLE 4.3.,.,-:

n.' <

SEISMIC MONITORING INSTRUMENTATION SURVE!LLANCE REQUIREMENTS CHANNEL CHANNEL FUNCT10NAL CHANNEL INSTRUMENTS AND_ SENSOR LOCATIONS CHECK TEST CAtlBRATION c.

Tr! axial Seismic Trigger (S/T)

1) XSH-VA-001 (Activates N.A.

SA R

ltems 1.b.1) thru 5) above) 2.

Triaxial Peak Recording Accelerograph (P/A's) a.

XR-VA-151 Reactor Equipment N.A.

N.A.

l (Top of reactor vessel head) b.

XR-VA-152 Reactor Piping N.A.

_N.A.

R (Mn. Stm. Line 'D,'-El 313'.

in containment) c.

XR-VA-153 Reactor-Equipment _

N.A.

N.A.

R Outside Containment (RHR Heat Exchanger, Loc. 20. R15-201) 3.

Triaxial Seismic Switches a.

XSHH.VA-001 Primary Containment N.A.

SA R

Foundation (Loc. Il8-R16-177) 4 Triaxial Response Spectrum Analyzer N.A.

SA R

(RSA)

  • The calibration frequency for this instrument is once per 24 months.

LlHfRICK - UNIT 2 3,' 1 ' 7?

' Amendment No. 21

a"*/

2' "n 2H W

' 3/4.4.2 SAFE 1YIRELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.2 The safety valve function of at least 11 of the following reactor coolant system safety / relief valves shell be OPERABLL with the specified code safety valve function lift settings:*#

4 safety / relief valves @ 1130 psig 1 %

1 5 safety / relief valves @ 1140 psig 11%

5 safety / relief valves @ 1150 psig 11%

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

A.

With the safety valve function of one or more of the above required safety / relief valves inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within-the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.

Withoneormoresafety/reliefvalvesstuckopeg,providedthatsuppression pool 'iverage water temperature is k s than 105 F, close the stuck open safety /relie# valve (s);ifunabletoclosetnestuckopenvalvefs)within2 minutes or if suppression pool average water temperature is 110 f or greater, place the reactor mode switch in the Shutdown position.

c.

W'th one or more safety / relief valve acoustic monitors inoperable, restore the ira 'able acoustic monitors to OPERABLE status within 7 days or Le 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 /> and in COLD SHUT 00Wh within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

l SURVEILLANCE REQUIREMENTS 4.4.2.1 The acoustic monitor for each safety / relief valve shall be d monstrated OPERABLE with the setpoint verified to be 0.20 of the full open noise level ## a performance of a:

a.

CHANNEL FUNCTIONAL TEST at least once per 31 days, and a i

b.

rHANNEL CALIBRATION at least once per 13 months **.

4.4.2.2 At least 1/2 of the safety relief valves shall be removed, set pressure tested dnd reinstalled or replaced with spares that have been previously set pressure tested and stored in accordance with manufacturer's recommendations at least once per 24 months, and l-they shall be rotated such that all 14 safety relief valves are removed, set pressure tested and reinstalled or replaced with spares that have been previously set pressure tested and stored in accordance with manufacturer's recommendations at least once per 54 l

months, The lift setting pressure shall correspond to ambient conditions of the Valves at nominal operating temperatures and pressures.

The provisions of Specification 4.0.4 are not applicable provided the Surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure is ddeQuate to perform the test.

Up to 2 incuerable valves may be replaced with spare OPERABLE valves with lower setpoints until the next refueling.

Initial setting shall be in accordance with the manufacturer's recommendation.

Adjustment to the valve full open noise level shall be accomplished during the startup test program.

LIMERICK - UNIT 2 3/4 4-7 Amendment No.21

. ~.

J REACTOR COOLANT SYSTEM 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS 1

LIi4ITING CONDITION FOR OPERATION 3.4.3.1 The following reactor coolant system leakage detection systems shall be 00ERABLE:

The primary containment atmosphere gaseous radioactivity monitoring a.

system, i

b.

The drywell floor drain sump and drywell equipment drain tar.k flow monitoring system, The drywell unit coolers condensate flow rate monitoring system, and c.

i d.

The primary cont.oment teess"*e and temperature monitoring system.

4 APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2 and 3.*

4 ACTION:

With only three of the above.'equired leakage detection systems OPERABLE, operation may continue for up to 30 days provided grab samples of the contain-nent atmosphere are obtajned and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the required gaseous radioactive monitoring system, primary containment pressure and temperature monitoring system and/or the drywell unit coolers condensate flow rate munitoring system is inoperable; otherwise, 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 /> and in COLD SHUTOOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.4.3.1 The reactor coolant system leakage detection systems shall be demonstrated OPERABLE by:

Primary containment atmosphere gaseous radioactivity monitoring a.

systems performance of a CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, a CP5NNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months, b.

The primary containment pressure shall be monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and the primary containment temperature shall be monitored at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c.

Drywell floor drain sump and Drywell equipment drain tank flow monitor-ing system performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION TEST at least once per 18 months.

d.

Drywell unit coolers condensate flow rate monitoring system.

i performance of a CHANNEL FUNCTIONAL TEST at least once per'31 days and a CHANNEL CALIBRATION at least once per 18 months.

LIMERICK - UNIT 2 3/4 4-8 l

--

Retrieved from "https://kanterella.com/w/index.php?title=ML20114B916&oldid=4290425"