ML20064K381
| ML20064K381 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 11/19/1980 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20064K383 | List: |
| References | |
| NUDOCS 8012010078 | |
| Download: ML20064K381 (20) | |
Text
..
/,.,'o UNITED STATES i\\$ s. f [' g NUCLEAR REGULATORY COMMISSION g
WASHING TON, D. C. 20555
-N M [/
%v PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY
_0_ELPARVA POWER AhD LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-277 PEACH BOTTOM ATC"C POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY CPERATING LICENSE Amend. ment No.75 License No. DPR-44 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated August 8,1980, as supplemented October 3, 1980, 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 facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Ccmmission; 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 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.
2.
Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment
/
and paragraph 2.C.(2) of Facility Operating License No. DPR-44 is hereby amended to read as folicws:
Technical Scecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.75, are hereby incorporated in the license.
PEC0 shall operate the facility in accordance with the Technical Specifications.
8012010 OW
_2 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY C0fVilSSION
-V/ kOW x
ert W. Reid, Chief Operating Reactors Branch t4 Division of Licensing Attachmenc:
Changes to the Technical Specifications Cate of Issuance: flovember 19, 1930 s
I I
ATTACH!!ENT TO LICENSE AMENDMENT NO. ?5 FACILITY OPEPATING LICENSE N0. DPR-44
?
DOCKET NO. 50-277 i
Replace the following pages of the Appendix "A" Technical Specifi-cations with the enclosed pages.
The revised pages are identified by anendment number and contain vertical lines indicating the area of change.
Insert Pages Renove Pages iii J
iii i
vii (new page) 240n-240q (new pages) 257 257 b
l
't i
(
e
PBAPS TABLE OF CONTENTS' (cont'd) 1 SURVEIID.NCE LIMITING CONDITIONS FOR OPEFATION R EQ UIR EMENTS PAGE NO.
3.1C FIRE PROTECTION 4.14 240c A.
Water Fire Protection System A
240c B.
CO2 Fire Protection System B
240g C.
Fire Detection C
240i D.
240j 3.15 SEISMIC MONITORISC INSTRD!I2iTATION 4.15 240n S.0 MAJOR DESIGN FEATURES 241 6.0 ADMINIS'IRATIVE CONTROLS 243 6.1 Responsibilit y 243 6.2 organi:r.ation 243 6.3 Facility Staff Qualifications 246 6.4 Training 246
- 6. S Review and. Audit 246 6.6 Reportable Occurrence Action 253 6.7 Safety Limit violation 253 6.8 Procedures 253
- 6. 9 Reporting Requirements 254 6.10 Record Retention 260 6.11 Radiation Protection Program 261 6.12 Fire Protection Inspections 261 6.13 High Radiation Area 262 6.14 Integrity of Systems Outside Containment 263 6.15 Iodine Monitoring 263 6.16 Environrental Qua'lification 264 Amend =ent No.,3% y?', J4( 75
-111-
PBAPS UNIT 2 LIST
' TABLES Table Title Page 3.15 Seismic Monitoring Instrumentation 240(o) 4.15 Seismic Monitoring Instrumentation 240p Surveillance Requirements._
i i
6 i
i i
i f
I i
- Ar:endment flo. 75
_vii.
i PI;n PS
.:!I T I::G C O :: D I T I O N S F03 0?E2ATIO1 SURVE!L:A CE REQUIREMENTS 3.15 Seismic Monitoring 4.15 Seismic Monitoring I n s t r a m e n t a t i o r.
Instrumentation Applicability Applicability Applies to the operational Applies to the surveillance status of the seismic requirements of the seismic monitoring instrumentation.
monitoring instrumentation.
Sp2cifications Snecifications A.
The seismic monitoring A.
Each of the required instrumentation
- shown in seismic mo71toring instruments Table 3.15 shall be shall be d e mons t ra t e d o pe ra ble.
operable by the performance of the Instrument Check, 3.
With one or more seismic Instrument Functional Test, menitoring instruments and Instrument Calibration inoperable for more than operations at the frequencies 30 days, in lieu of any shown in Table 4.15.
other report
- r. squired by Specification 6.9.2, S.
Each of the seguired prepare and submit a seismic moni oring instruments Special Report to the actuated during a seismic Director of the event shall be restored to appropriate Regional O f fice operable status within 24 pursuant to Specification hou rs and an Instrument 6.9.3 with.in the next 10 Calibration performed within working days outlining the 5 days following the seismic cause of the ma lf unc tion event. Data shall be and the plans for restoring retrieved from actuated the instrument (s) to instruments and analyzed to operable status.
determine the magnitude of the vibratory ground motion.
C.
The provisions of Specification In lieu of any other report 3.0.c are not applicable.
required by Specification 6.9.2, a S pecial aeport shall be prepared and submitted to the Director of the appropriate Regional Office pursuant to Specification 6.9.3 within 10 working days describing the magnitude, frequency spectrum and resultant effect upon facility features important to safety.
Artndment flo. 75
-240n-
-,..r-s
T A n l.r.
3.15 *
- r r,1 s. I C "n r 1 TO:t I ::C I !: S T R t' 17.l:T A T I O *I
!!!ninun l
- le a s u re nc u t Instrunents Instrunents and 9ensor Ior.ations#
ttanne Oncrable_ _
l.
Triaxial T i n e-!! i s t o r y Ac c e l e r o c, r a p h s n.
Containment Foundation (torus compartneut)
O.1-10p, 1
b.
'i c f u e l i n g rioor 0.1-10n 1
c.
RCIC Punp (nn il 7 )
0.1-10g I
d.
"C" Diesel Cencrator O.1 - 10 :;
1
/
2.
Triaxial Peak A c c e l e r o a, r a p h s a.
l'eactor Piping (Drywell) 0.01-2o, I
h.
Refuelinn Floor 0.01-2p, I
c.
"C" Diesel Generator 0.01-2g 1
3.
Triaxial R e s p on s e-S p e c t r uin 11ecorders a.
Cahic Spreading Rn 0.1-10g 1*
l l
'J i t h reactor control roon annunciation j
- Cffective upon conpletion of installation.
Scisnic ' instrumentation located in Irnit 2 f
i l
i Amendment No. 75
-240(o)-
N O
d i
T A ft LE 4.15**
S E I G:11 C *!n!:I To tt i t;G I! STR U;tE:! TAT IO?! S U R V E I L L A *:C E R Cif U I R E :t E '!T S Instrument *-
Instrisment*
Functional Instrument
- Instruuents and Sensor 1,ocations#
Check Test Calibration 1.
Triaxial Time-!!istory Accelerographs a.
Containment Foundation (torus c o at p a r t m e n t )
1:
SA R
b.
't e f u e l i n,a, F l o o t-SA R
c.
DCIC Pump (Rn #7)
SA R
d.
"C" Diesel Generator
't SA R
2.
Triaxial Peak Acceleror,raphs l
r a.
Reactor P i p i n !; (Drywell) ilA tiA R
l
]
h.
Refueling Floor
??A t!A R
c.
"C" Diesel Generator il A
'4 A R
3.
Triaxial P e s p o,n s e-S p e c t ris m Recorders i
n.
Cable spreading it ra t!
SA R
4 j
Surveillance Frequencies ft:
every month SA:
every 6 months R:
every 18 montho j
Effectiw..lon completion of installation.
l 9 Seismic O.c;rumentation located in Unit 2.
1 A=endmen: :;o.
70
-240p-i 1
E i
1 4
1 n
PBAPS 3.15/4.14 BASES ine operability of the seismic monitoring instrumentation ensures that sufficient capability is available to promptly determine the magni-tude cf a seismic event and evaluate the response of those features irocr: ant to safety. This capability is required to permit comparison of the r.easured response to that used in the design basis for the plant.
Tne time-history recordings of the triaxial time-history accelero-graphs are done in the cable spreading room on a digital cassette accelero-graph.
In addition to being recorded, the containment foundation sensor is analy:ed on line by a response spectrum analyzer.
The spectrum of any sensor can be obtained by playing back its tine-history cassette through the response spectrum analyzer.
l Arendrent No. 75
-240q-l
P3nPS 5.7.2 Continued (3) Observed i n a d e q u a s:i e s in the imple=entation of administrative or procedural controls which threaten to,cause reduction of degree of redundancy p ro vi dti d in reactor protection systems or engineered saf nty feature systems, (4) Abnormal degradation of systems other than those specified in item 2.a(3) above designed to contain radioactive ma t e r:.a 1 process.
resulting from tha fission y
Note: Sealed sources or calibration sources are not included under this item.
Leakage of valve packing or gaskets. within the limits for identified leakage set forth in technical specifications need not be reported under this ite=.
5.9.3 Unicue Reporting Recuiremencs Special reports shall be submitted to the Director of the appropriate Regional Office within the time period specified for each report.
These reports shall be submitted covering the activities identified below pursuant to the requitecerts of the applicable reference specification:
a.
Loss of shutdown margin, Specification 3.3.A and 4.3.A within 14 days of the event.
b.
Reactor vessel inservice inspection. Specification 3.6.C and 4.6.G within 90 days of the completion of the reviews.
c.
Report seismic monitoring instrumentation inoperable for more than 30 days (Specification 3.15B) within the next 10 working days.
Submit a seismic e vent analysis (Specification 4.15B) within 10 vorking days of the e ve n t.
d.
Primary containment leak rate testing approximately three months after the completion of the periodic integrated leak race test (Type A) required by Specification 4.7.A.2.c.2.
For each period!c test, leakage test results from Type A, B and C tests shall be reported.
B and C tests are local leak rate tests required by Specification 4.7.A.2.f.
The report shall contain an analysis and interpretation of the Type A test results and a summary analysis of periodic Type 3 and Type C tests that were performed since the last Type A test.
Aneneen: no. 27, g p/ 75
-237-1 e
a ntsc o,
UNITED STATES
- .j '{
i j
NUCLEAR REGULATORY COMMISSION
%g r
WASHINGTON, D. C. 20555 f
+,
Jr PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS C6MPANY
_DELMARVA PCWER A.ND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPA.N_Y DOCKET NO 50-278 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 AMEN 0HENT TO FACILITY OPERATING LICENSE Amendment No.74 License No. DPR-56 1.
The Nuclear Regulatory Conmission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Corgany, et al. (the licensce) dated August 8,1980,,as supplemented October 3, 1930, cocalles with the standards and requirements of the Atocic Energy Act of 1954, as amended (the Act), and the Cornission'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 Ccmmissien; C.
There is reasonable assurance (1) that the activities autherfred by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be concucted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense anc 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.
2.
Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment and caragraph 2.C.(2) of Facility Operating License No. DPR-56 is hereby amended to read as follows:
Technical Soecifications The Technical Specifications contained in A,.
?- a. and B, as revised through Amendment Nc. 74, are hereby incorporated in the license. PECO shall operate the facility in accordance with the Technical Specifications.
9 w
r r
-2 3.
This license amendment is effective as of the date of its issuance.
FOR THE ftUCLEAR REGULATORY COMf11SS10ti x n/ 3
./
n (a
^
%./
x'obertW.Reid, Chief R
Operating Reactors Branch f4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
t!ovember 19, 1930 I
l
i ATTACHf:ENT TO LICENSE AMENDMENT NO. 74 FACILITY OPERATING LICENSE NO. DPR-56 DOCKET NO. 50-278 Replace the r'ollowing pages of the Appendix "A" Technical Specifi-cations with the enclosed pages.
The revised pages are identified by arendment number and contain vertical lines indicating the area of change.
Remove Pages Insert Pages iii iii vii (new page) 240n-240q (new pages) 257 257
PBAPS TABLE OF CON"'ENTS* (cont' d)
SURVE!LIJ.NCE LIMITING CO!CITIONS FCE OPERATION REQUIR EME;TS PAGE NO.
3.14 FIRE PROTECTION 4.14 240=
A.
Water Fire Prot -ction Syste:
A 240c E.
CO2 F.' re Protec ion Syste=s 3
240g C.
Fire Letection C
240i D.
240j 3.15 SE:S::IC MONITOR:::G INST;CENTATION 4.13 240 5.0 MMOR DESIGN FIA"URIS 241 6.0 ADMINIS EATIVE CONTROI.S 243 6.1 Responsixd*y 243 6.2 Organization 243 6.3 Facility Staff Qualifications 246
- 6. 4 Training 246
- 6. 5 Review and. Audit 246 6.6 Repor aile Occurrence Ac ion 253 6.7 safety Lir.it violation 253
- 6. S Procedures 253
- 6. 9 Reporting Require:.eM.s 254 6.10 Record Retention 260 6.11 Radiatien Protection Program 261 6.12 Fire Protection Inspe=tions 261 6:13 Eigh Radiation Area 262 6.14 integrity of Systems Outside Containment 263 6.15 Iodine Monitoring 263 6.16 Environmental Qualification 264 D *
- l[)
9 ]g
' Q M JA M m_
l f
l
(
A=end=ent No. 39. 47', 75, 74
a j
PBAPS UNIT 3 i
I LIST OF TASLES 4
Table Title Page j'
3.15 Seismic Ponitoring Instrumentation 240(o) 4.15 Seismic Monitoring Instrumentation 240p Surveillance Requirements i
t j
.c f
p J
' n.inent.No.-74
-vii-
PunPS Lif.ITINO CONDITIONS FOR OPERATIOli SURVEILLANCE REQUIREMENTS 3.15 Seismic Monitorine 4.15 Seismic Monitoring I r. s t r u m e n t a t i o n Instrumentation Applicability Applicability Applies to the operational Applies to the surveillance status of the seismic requirements of the seismic monitoring instrumentation.
monitoring instrumentation.
Soecifications Specifications A. The seismic monitoring A.
Each of the required ins t rument a tion' s hown in seismic monitoring instruments Table 3.15 shall be
,,shall be demonstrated operable.
operable by the perfor=ance, of the Instrument Check,
- 3. With one or more seismic Instrument Functional Test, monitoring instruments and Instrument Calibration in perable for more than operations at the frequencies 53 days, in lieu of any shown in Table 4.15.
ether report required by Specification 6.9 2,
3.
Each of the required p repare and submit a seismic monitoring instruments 5pacial Report to the actuated during a seismic Director of the event shall be restored to ap;ropriate Regional Office operable status within 24 pursuant to Specification hours and an Instrument
6.9.3 withi
the next 10 Calibration performed within werking days outlining the 5 days following the seismic cause of the malfunction event. Data shall be and the plans for restoring retrieved from actuated the instrument (s) to instruments and analy=ed to operable status.
determine the magnitude of the vibratory ground motion.
C.
The p ro visions of Specification In lieu of any other report 3.0.c are act applicable.
required by Specification 6.9.2, a Special Report shall be prepared and su bmi t te d to the Director of the appropriate Regional Office pursuant to Specification 6.9.3 within 10 working days describing the magnitude, frequency spectrum and resultant effect upon facility features important to safety.
A c.q: ent No. 74
-240n-w m
~
i T A lti.E 3.15**
S C I S ?tI C "O t:I TO:11 NG I N S T P. U!!E t:T AT I O N
!!inimum
- lea s u re me n t Instrunents Instruments and Sensor 1,ocations#
It a n c.e Operable 1.
T rinxial T ine-!!is t ory Accele rogra phs a.
Containment Fountiation (torus compartment) 0.1-10g I
h.
Refueline, Floor 0.1-10g I
c.
RCIC Punp (Rn #7) 0.1-10g 1
d.
"C" Diesel Generator 0.1-10; I*
2.
Triaxial Peak Acceleror,raphs a.
Itenctor Piping (Drywell) 0.01-2q l
h.
Refueling Floor 0.01-2p, I
c.
"C" Diesel Generator 0.01-2r, 1
3.
Triaxial Response-Spectrum Recorders a.
Cable Spreading Rm 0.1-10g 1*
ti t t h reactor control rdom annunciation
- Effective upon completion of installation.
Seismic instrunentation located in Unit 2 d
ei 9
3 4
Amendment No. 74
-240(o)-
.i k
TABLE 4.1S**
S C I S'll C ?!O!;1 TO R I NG I N S T R U tlF.N T A T I O N S U RV E I L L A *:C E R CQ U I R E'!E NT S Instrument
- Instrument
- Functional Instrument
- Instruments and P. e u s o r Locations #
Check,
_ Test Calibratfor.
1.
T r ia xial T ime-flis t ory A c c e l e r o r. r a ph s a.
Cnntainment Foundation (tnrus conpartnent)
SA P.
h.
- lefueling Floor
?!
SA R
c.
PCIC Pump (Rn #7)
SA R
.d.
" C '* Diesel Generator
't SA R
2.
Triaxial Peak Accelerographs a.
Reactor Piping, (Drywell)
NA NA R
h.
f:efuelint', Floor NA NA R
i c.
"C" Diesel Generator NA NA R
3.
Triaxial Response-Spectrun Recorders a.
Cable S preadian Ra il SA R
Surveillance Frequencies every month i
SA:
every 6 months R:
every 18 months
. Effective upon completion of installation.
Seis=ic instrumentation located in Unit 2.
i A
l
-240p-Amendment No.
74 l-l i
I
i e
i PBAPS 3.15/4.14 BASES The operability.of the seismic ronitoring instrucentation ensures that sufficient capability is available to promptly determine the magni-tude of a seismic event and evaluate the response of those features important to safety.
This capability is required to permit cor.;arison of the measured response to that used in the design basis for the plant.
i The time-history recordings of the triaxial tine-history accelero-graphs are done in the cable spreading room on a digital cassette accelero-gra ph.
In addition to being recorded, the containment foundation sensor is analyzed on line by a response spectrum analyzer.
The spectrum of any sensor can be obtained by playing back its tine-history cassette through the response spectrum analyzer.
4 l
Amendment No. 74
-240q-
~~
l l
PL.PS 6.9.2 Continued (3) Observed inadequacies in the implemas ation of administrative or procedural controls which threaten to,cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems.
(4) Abnormal degradatton of systems other than those specified in item 2.a(3) above designed to contain radioactive material resulting from the fission process.
Note: Sealed sources or calibration sources are not included under this item.
Leakage of valve packing or gaskets: within the limits for identified leakage set forth in technical specifications need not be reported under this item.
6.9.3 Unioue Reporting Recuirements Special reports shall be submitted to the Director of the appropriate Regional Office within the ti=e period specified for each report.
These reports sha'1 be submitted covering the activities identified.elow pursuant to the requiremer c s of the applicable reference specification:
a.
'yoss of shutdown margin, Specification 3.3.A and 4.3.A within 14 days of the event.
b.
Reactor vessel inservice inspection, Specification 3.6.G and 4.6.G within 90 days of the completion of the reviews.
c.
Report seismic monitoring instrumentation inoperable for more than 30 days (Specification 3.158) within the next 10 working days.
Submit a seismic event analysis (Specification 4.15B) within 10 working days of the event.
d.
Primary containment leak rate testing approximately three months after the completion of the periodic integrated leak rate test (Type A) required by Specification 4.7.A.2.c.2.
For each periodic test, leakage test results from Type A, B and C tests shall be reported.
3 and C tests are local leak race tests required by Specification 4.7.A.2.f.
The report shall contain an analysis and interpretation of the Type A test results and a summary analysis of periodic Type 3 and Type C tests that were performed since the last Type A test.
Amendment No. g [ g 74
-257-
.