ML19320D023
| ML19320D023 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 07/16/1980 |
| From: | Kemper J PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML19320D020 | List: |
| References | |
| NUDOCS 8007180446 | |
| Download: ML19320D023 (18) | |
Text
,
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M.
BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION In the Matter of Docket Nos. 50-277 PHILADELPHIA ELECTRIC COMPANY 50-278 APPLICATION FOR AMENDMENT OF FACILITY OPERATING LICENSES DPR-44 & DPR-56 Edward G. Bauer, Jr.
Eugene J. Bradley 2301 Market Street Philadelphia, Pennsylvania 19101 Attorneys for Philadelphia Electric Company 8007180 Nld
.4
.a BEFORE Tile UNITED STATES NUCLEAR REGULATORY COMMISSION In the Matter of Docket Nos. 50-277 50-278 PilILADELPHIA ELECTRIC COMPANY 1
j APPLICATION FOR AMENDMENT l
0F FACILITY OPERATING LICENSES j
DPR-44 & DPR-56 Philadelphia Electric Company, Licensee under Facility Operating Licenses DPR-44 and DPR-56 for Peach Bottom Units 2 and 3, hereby requests that the Technical Specifications contained 'n Appandix A of the Operating Licens,es be amended by revising certain sections as indicated by a vertical bar in the margin of attached pages 180, 186, 187, and 257a.
I.
Control Rod Drive Return Line Modification In a Philadelphia Electric Company operating license amendment request dated August 27, 1979, we indicated our intentions to cut and cap the Control Rod Drive Return Line (CRD RL) on Unit 3 during the fall, l')79 ref ueling ouca' 1, and to expedite the re-routing as soon as practicable but not later than I
the end of the next Unit 3 refueling outage.
Our submittal i
further stated that the entire modification for Unit 2 was planned for the Spring, 1980 refueling outage.
K.,
acceptance of this proposal was issued in Amendment Nos. 60 and 60 to Facility Operating License Nos. DPR-44 and DPR-56 for the Peach Bottom Atomic Power Station Units 2 and 3.
The amendments revised the table of Primary Containment Isolation Valves to reflect the re-routing of the CRD-RL to the Reactor Water Cleanup System.
A letter to E.
G.
Bauer, Philadelphia Electric Company, from R.
L.
Baer of the NRC, dated March 13, 1980, identified NRC i
acceptance of capping the CMU return line without rerouting providing the following conditions are met:
1.
Concurrent two CRD pump operation is demonstrated by testing.-
2.
Equalizing valves are installed between the cooling water header and the exhaust water header.
3.
Flush ports installed at high and low points of the exhaust water header piping run if carbon steel piping is retained.
4.
Carbon steel pipe in the flow stabilizer loop is replaced with stainless steel.and rerouted directly to the cooling water header.
Based on ou r e nginee ring as ses,sment and discussions with the NRC licensing staff, we are proposing that the option involving CRD Return Line capping without rerouting, in accordance with the i
March 13, 1980 letter, be selected for implementation.
Conditions 1 and 2 would be implemented as described above.
Independent engineering calculations by Philadelphia Electric Company and Ceneral Electric Company have provided reasonable
. confidence that the'two CRD pump operation test (condition 1) 1 ek J
will actisfy the NRC flow criteria.
Stainless steel is utilized I
for the exhaust water. header piping at Peach Bottom; therefore, condition 3 is not applicabic to our design.
Filters, with high differential pressure alarms, are presently installed for protection of the control rod drives from carbon steel corrosion product carryover from the stabilizer loop.
These filters are not in a location where their clogging would interfere with the cooling flow, and should alleviate the need to change material as described in condition 4.
Therefore, we propose that condition 4 not be applicable for the Peach Bottom design.
Conditions 1 and 2 would be implemented on Unit 2 during the current refueling outage, and on Unit 3 during the next scheduled refueling outage.
Accordingly, the Licensee requests that Table 3.7.1 (page 180) be amended to reflect the proposal not to reroute the CRD Return Line, by' deleting the control' rod hydraulic isolation valves and the applicable notes at the bottom of the page, which are in response to the R.
L.
Baer letter of March 13, 1980.
II. Containment Isolation Valve Modifications - CAD Piping Additional containment isolation valves in the radioactive gas sampler line, and in the instr'ument nitrogen compressor auction line will be installed at Units 2 and 3 to meet the requirements of item 2.1.5.a of NUREG 0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations."
There are presently two isolation valves on both the radioactive gas sampler line and the instrument nitrogen compressor suction line.
Ilow e ve r, during operation of the _
Containment Atmospheric Dilution (CAD) system, one of these valves will be open and only one valve will remain closed.
Therefore, an inboard isolation valve SV-8100 (SV-9100) will be added in series with Valve A0-4235 (AO-5235) in the instrument nitrogen compressor suction line, and an outboard isolation valve, SV-8101 (SV9101) will be added in the radioactive gas sampler line downstream of the header that connects all four sample lines SV-4966 A-D (SV-5966 A-D).
The addition of these valves will ensure redundant isolation of the subject lines during CAD system operation.
NRC acceptance of these modifications was provided in an evaluation report of Philadelphia Electric Company's actions to satisfy the Category "A"
items of NUREG 0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendatio+
(T.
A.
Ippolito, NRC, to E.
G.
Bauer, Philadelphia Electric Company, dated February 26, 1980).
Accordingly, the Licensee requests that Table 3.7.1, page 180, and Table 3.7.4 page 186 and 187, be revised as indicated by the vertical bar in the margin to include these valves as primary containment isolation valves.
Schematics of these modifications are attached for your information.
111 Containment Isolation Valve Modifications Breathing Air System Philadelphia Electcic Conpany proposes that a permanent breathing air header system be installed in the Peach Bo.ttom Unit 2 and Unit 3 drywells du ring a future outage.
These systems will
]
l
. j
accommodate maintenance activities in contaminated creas.
The air supply piping will enter the containment using a spare containment penetration.
The penetration will be equipped with locked closed valves, and provided with test connections to facilitate local leak rate testing.
Accordingly, the Licensee requests that Tabic 3.7.4 of the Technical Specifications be revised as indicated by the vertical bar in the margin of attached page 187 to include these valver as primary containment isolation valves.
A sketch of the proposed breathing air system is attached for your information.
IV. Typographical Error The proposed change to page 257a corrects a typographical error in a reference to another specification by changing 3.13.3 to 3.13.2.
Pursuant to 10 CFR 170.22 " Schedule of Fees for l
Facility License Amendment", Philadelphia Electric Company proposes that this Application for Amendment be considered a class II Amendment for Unit 2 and a class I amendment for Unit 3, since the proposed changes are deemed to be administrative in nature.
The Plant Operation Review Committee and the Operation and Safety Review Committee have reviewed these proposed ts.
J
+
changoc to the Technical Specifications and have concluded that they do not involve an unreviewed safety question or a significant hazards co'nsideration and will not endanger the health and safety of the public.
Respectfully submitted, Pl!ILADELPilIA ELECTRIC COMPANY
($ 6 // L _
V1'ce President s4 c.
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COMMON 11EALTil 0F PENNSYLVANIA ss.
COUNTY OF Pl!ILADELPHIA i
J.
S.
Kemper, being first duly sworn, deposes and says:
r l'
That he is Vice President of Philadelphia Electric 1
i Company, the Applicant herein; that he has read the foregoing Application for Amendment of Facility Operating Licenses and knows the contents thereof; and that the statements and matters set forth therein are true and correct to the best of his knowledge, information and belief.
$ W W.
f.
/
/
Subscribed and sworn to before me'this l day of h
/
l M
ary Publ i(
[l EL BETH H. BOY y Public. Phila., Phila. Co.
My Commlaston Expires.Jan. 30,1982 1
CERTIFICATE OF SERVICE I certify that service of the foregoing Application was made upon the Board of Supervisors, Peach Bottom Township, York County, Pennsylvania, by mailing a copy thereof, via first-class mail, to Albert R. Steele, Chairman of the Board of Supervisors, R. D. No. 1, Delta, Pennsylvania 17314; upon the Board of Supervisors, Fulton Township, Lancaster County, Pennsylvania, by mailing a copy thereof, via first-class mail, to George K.
Crinton, Chairman of the Board of Supervisors, Peach Bottom, Pennsylvania 17563; and upon the Board of Supervisors, Drumore Township, Lancaster County, Pennsylvania, by mailing a copy thereof, via first-class mail, to Wilmer P. Bolton, Chairman of the Board of Supervisors, R. D. No.
1, Holtwood, Pennsylvania 17532; all this 16th day of
- July, 1980 l
=w
'ugen J. Bridley Atto ney for Philadelphia Electric Company
TABLE 3.7.1 (Coat'd.)
PRIMARY CONTAINMENT ISCLATICN VALVES I
Number of. Power Maximum Action on Operated Valves Operating Normal Initiating Group Valve Identification Inboard outboard Time (sec.)
Position Signal NA Feedwater check valves 2*
2*
NA 0
Process 3
Radioactive gas sample isolation 4
l#
NA C
SC valves 3
Instrument nitrogen compressor l#
1 5
0 GC suction line isolation valves t
3
! Oxygen Analyzer System 14 NA 0
i GC NA Standby liquid control system 1*
1*
NA C
I Process check valves t
2B '
RHRS shutdown cooling suction 1
1 32 C
SC isolation valves 2B RHRS shutdown cooling 1
24 C
SC injection isolation valves 2B RHRS Reactor Vessel Head Spray 1
1 30 C
SC isolation valves l
2C Feedwater Flash Valves 2
50 C
SC i
4 HPCIS steam line isolation 1
1 20 0
l CC valves I
5 RCICS steam line isolation 1
1 15 0
CC valves 2A Reactor water cleanup system 1
1 30 0
GC isolation valves f
2A Reactor water cleanup system 1
20 0
GC L
return isolation valve g
j i
- valves not power operated.
- Effective upon completion of the modification required by NUREG 0578, iteu 2.1.Sa
7 PBAPS Unit 2 TABLE 3.7.4 (Cont'd.)
PRIMARY CONTAINMENT TESTABLE ISOLATION VALVES Pen No.
Notes 22 AO-2969A; Check Valve (1)(2)(4)(5)(10) 25 AO-2520; AO-2505; AO-2519; (1)(2)(4)(5)(9)
J AO-2521A; AO-2521B 25 AO-2523; Check Valves (1)(2)(4)(5) 26 AO-2506; AO-2507 (1)(2)(4)(5)(9) 26 SV-2671G; SV-2978G (1)(2)(4)(5) 26 AO-2509; AO-2510; AO-4235 (1)(2)(4)(5)(9) 26 SV-4960B; SV-4961B; SV-4966B (1)(2)(4)(5) 26 SV-8100*
(1)(2)(4)(5) 26, 51C SV-8101*
(1)(2)(4)(5) 203, 219 39A MO-10-31B; MO-10-26B (1)(2)(4)(5)(9) 39A SV-4949B; SV-4948B (1)(2)(4)(5) 39B MO-10-31A; MO-10-26A (1)(2)(4)(5)(9) 39B SV-4949A; SV-4948A (1)(2)(4)(5) 41 AO-2-3 9 ; AO-2 -4 0 (1)(2)(4)(5)(9) 42 Check Valve 11-16, XV-14A, XV-14B (1)(2)(4)(5)(10) 51A SV-2671E; SV-2978E (1)(2)(4)(5) y SlB SV-2671D; SV-29780 51C SV-2671C; SV-2978C 51C SV-4960C; SV-4961C; SV-4966C 51D SV-2980; Check Valve 52F AO-2969B; Check Valve (1)(2)(4)(5)(10) l 57 AO-2-316; AO-2-317 (1)(1)(4)(5)(9) l 102B Breathing Air System-2 Gate (1)(2)(4)(5)(9) l Valves
- l l
203 SV-2671B; SV-2978B (1)(2)(4)(5)
-186-
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PBAPS Unit 7 TABLE 3.7.4 (Cont'd.)
PRIMARY CONTAINMENT TESTABLE ISOLATION VALVES Pen No.
Notes 203 SV-4966D; SV-4961D; SV-4966D 205A AO-2502B; Check Valve 9-26B (1)(2)(4)(5)(9) 205B AO-2dO2A; Check Valve 9-26A 211A MO-10-38B; MO-10-39B; MO-10-34B (1)(2)(4)(5)(9) 211A SV-4951B; SV-4950B (1)(2)(4)(5) 211B NO-10-38A; MO-10-39A; MO-10-34A (1)(2)(4)(5)(9) 211B SV-4951A; SV-4950A (1)(2)(4)(5) 212 Check Valve 13-50; AO-4240; AO-4241 (1)(2)(4)(S)(9) 214 Check Valve 23-65; AO-4247; AO-4248 (1)(2)(4)(5)(9) 217B MO-4244; h0-4244A (1)(2)(4)(5)(9) 218A AO-2968 (1)(2)(4)(5)(10) 218B SV-2671A; SV-2978A (1)(2)(4)(5) 219 AO-2511; AO-4512; AO-2513; AO-2514 (1)(2)(4)(5)(9) 219 SV-2671F; SV-2978F; SV-4960A (1)(2)(4)(5)
SV-4961A; SV-4966A 221 Check Valve 13-38 (1)(2)(4)(5)(9) 223 Check Valve 23-56 (1)(2)(4)(5)(9) 225 MO-13-41; MO-13-39 (1)(2)(4)(5)(9) 225 MO-14-70; MO-14-71 (1)(2)(4)(5)(9) 227 MO-23-58; MO-23-57 (1)(2)(4)(5)(9)
- Effective upon completion of the modification
-187-
. ~.
PBAPS Unit 3 TABLE 3.7.4 (Cont'd.)
PRIMARY CONTAINMENT TESTABLE ISOLATION VALVES Notes Pen No.
22 AO-3969A; Check Val'/e (1)(2)(4)(5)(10) 25 AO-3520; AO-3505; AO-3519; (1)(2)(4)(5)(9) j AO-3521A; AO-3521B 25 AO-3523; Check Valves (1)(2)(4)(5) 26 AO-3506; AO-3507 (1)(2)(4)(5)(9) j 26 SV-3671G; SV-3978G (1)(2)(4)(5) 26 AO-3509; AO-3510; AO-5235 (1)(2)(4)(5)(9) 26 SV-5960B; SV-5961B; SV-5966B (1)(2)(4)(5) 26 SV-9100*
26, 51C SV-9101*
203, 219 39A MO-10-31B; MO-10-26B (1)(2)(4)(5)(9) 39A SV-5949B; SV-5948B (1)(2)(4)(5) 39B MO-10-31A; HO-10-26A (1)(2)(4)(5)(9) 39B SV-5959A; SV-5948A (1)(2)(4)(5) 41 AO-2-39; AO-2-40 (1)(2)(4)(5)(9) 42 Check Valve 11-16, XV-14A, XV-14B (1)(2)(4)(5)(10) 51A SV-3671E; SV-3978E (1)(2)(4)(5) 51B SV-3671D; SV-3978D 51C SV-3671C; SV-3978C SIC SV-5960C; SV-5961C; SV-5966C 51D SV-3980; Check Valve 52F AO-3969B; Check Valve (1)(2)(4)(5)(10) 57 AO-2-316; AO-2-317 (1)(2)(4)(5)(9) 102B Breathing Air System-2 Gate Valves
- 4 203 SV-3671B; SV-3978B (1)(2)(4)(5)
-186-
PBAPS Unit 3 TABLE 3.7.4 (Cont'd.)
PRIMARY CONTAINMENT TESTABLE ISOLATION VALVES i
Pen No.
Notes 203 SV-5960D; SV-5961D; SV-5966D 205A AO-3502B; Check Valve 9-26B (1)(2)(4)(5)(9) 205B AO-3502A; Check Valve 9-26A 211A MO-10-38B; MO-10-39B; HO-10-34B (1)(2)(4)(5)(9) 211A SV-5951B; SV-5950B (1)(2)(4)(5) 211B MO-10-38A; MO-10-39As MO-10-34A (1)(2)(4){5)(9) 211B SV-5951A; SV-5950A (1)(2)(4)(5) 212 Check Valve 13-50; AO-5240; AO-5241 (1)(2)(~.)(5)(9) 214 Check Valve 23-65; AO-5247; AO-5248 (1)(2)t4)(5)(9) 217B MO-5'244; MO-5244A (1)(2)(4)(5)(9) 218A AO-3968 (1)(2)(4)(5)(10) 218B SV-3671A; SV-3978A (1)(2)(4)(5) 219 AO-3511; AO-3512; AO-3513; AO-3514 (1)(2)(4)(5)(9) 219 SV-3671F; SV-3978F; SV-5960A (1)(2)(4)(5)
SV-5961A; SV-5966A 221 Check Valve 13-38 (1)(2)(4)(5)(9) 223 Check Valve 23-56 (1)(2)(4)(5)(9) 225 MO-13-41; MO-13-39 (1)(2)(4)(5)(9) 225 MO-14-70; MO-14-71 (1)(2)(4)(5)(9) 227 MO-23-58; MO-23-57 (1)(2)(4)(5)(9) e Effective upon completion of the modification.
I
-187-
~
PBAPS 6.9.3 Continued e.
Release rate of Radioactive Effluents, Specification 3.8.B.7, 3.8.C.3.b, 3.8.C.S.
f.
Sealed source leakage in excess of limits, Specification 3.13.2 g.
Effluent Releases Effluent data should be summarized monthly, except in instances when more data is needed, and the items listed below reported semi-annually on the standard form " Report of Radioactive Effluents".
i 1)
Caseous Releases a)
Total radioactivity released (in curies) of noble and activation gases.
b)
Maximum noble gas release rate during any one-hou r period.
-257a-1 L
A0-2509 (3509)*
A0-2510 (3510)*
DRYWELL l
l CAD EXHAUST l N-26 l lNSTRUMENT N2 COMPRESSOR SV-8100 (9100)**
A0-4235 (5235)
SUCTION PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION VALVES MAY BE OPEN DURING ACCIDENT CONDITIONS UNITS 2 & 3 VALVES TO BE ADDED BY PROPOSED MODIFICATION.
ALL OTHER VALVES PRESENTLY EXIST AS SHOWN INSTRUMENT NITROGEN COMPRESSOR NOTE:
val.VE IDENTIFICATION NUMBERS FOR UNIT 3 SHOWN IN PARENTHESIS SUCTION LINE SCHEMATIC
TORUS
- c
- CAD ANALYZER A 4960A*
4961A*
(5960A)
(5961 A) 4 66A (5966A)
ORYWELL
- CAD ANALYZER D ua 4960B*
4961 B*
(59608)
(59618) 4 66B (59668)
RADIDACTIVE DRYWELL
- CAD ANALYZER C ua 4960C*
4961C*
SVB 01(9101) ** S PLER (59600)
(5961 C)
N-51C 4966C (5966C)
TORUS
- CAD ANALYZER D ta 4960D*
4S61 D*
(59600)
(59610)
N-203 49660 PHILADELPHIA ELECTRIC COMPANY (59660)
PEACH BOTTOM ATOMIC POWER STATION
- VALVES MAY BE OPEN DURING ACCIDENT CONDITIONS UNITS 2 AND 3
- VALVES TO BE ADDED BY PROPOSED MODIFICATION.
ALL OTHER VALVES PRESENTLY EXIST AS SHOWN.
RADIDACTIVE GAS SAMPLER NDTE:
VALVE IDENTIFICATION NUMBERS FOR UNIT 3 SHOWN IN PARENTHESIS LINE SCHEMATIC
s n
I E
NUCLEAR BOILER FROM COMPRESSED AIR SYSTEM THRU FILTRATION BOX &
PRESSURE CONTROL VALVE PIPING SILVER SOLDERED SEISMIC CLASS I L
l N-102B
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^
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3
3
N!/
M --
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BREATHING AIR l
CONNECTION BOX
,7 J
ONNECTION PHILADELPHIA ELECTRIC COMPANY.
PEACH. BOTTOM ATOMIC POWER STATION DRYWELL BREATHING AIR SYSTEM l