ML20062B862
| ML20062B862 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 10/03/1978 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20062A450 | List: |
| References | |
| NUDOCS 7811010400 | |
| Download: ML20062B862 (9) | |
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j UNITED STATES WUCLEAR REGULATORY COMMISSION y
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PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARYA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCXET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 AMEND?ENT TO FACILITY OPERATING LICENSE iD v
Amendment No. 46 License No. OPR-56 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applications for amendment by Philadelphia Electric Company, et al, (the licensee) dated May 6,1977 and March 14, 1978, as supplemented July 11, 1978, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set 2
forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the applicatic1, 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 amencment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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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-56 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 46, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the
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Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION V
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4 Thomas A.polito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 3,1978 t
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ATTACHMENT TO LICENSE AMENDMENT NO. 46 FACILITY OPERATING LICENSE NO. DPR-56_
DOCKET NO. 50-278 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert 4
iv iv 165 165 g
181 181 v
185 185 186 186 187 187 190 190 a,e P
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t PBAPS Unit 3 l
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i LIST OF FIGURES Fiqure Title Page 1.1-1 APRM Flow Bias Scram Relationship To 16 Normal Operating Conditions 4.1.1 Instrument Test Interval Determination 55 Curves 4.2.2 Probability of System Unavailability 98 Vs. Test Interval 3.4.1 Required Volume and Concentration of 122 Standby Liquid Control System Solution 3.4.2 Required Temperature vs. Concentration 123
( for Standby Liquid Control System Solution 3.5.1.A MAPLHGR Vs. Planar Average Exposure, 142 Unit 3, 7x7 Fuel, Type 3 t 3.5.1.B MAPLHGR Vs. Planar Average Exposure, 142a Unit 3, 7x7 Fuel, Type 2 3.5.1.C MAPLHGR Vs. Planar Average Exposure, 142b Unit 3, 8x8 Fuel, Type H 3.5.1.D MAPLHGR Vs. Planar Average Exposure, 142c Unit 3, 8x8 Fuel, Type L 3.5.1.E Kf Factor Vs. Core Flow 142d 3.5.1.F MAPLEGR Vs. Planar Average Exposure, 142e Unit 3, 8x8 FIA Fuel j 3.5.1.G MAPLHGR Vs. Planar Average Exposure, 142f Unit 3, 8x8R Fuel 3.6.1 Minimum Temperature for Pressure Tests 164 such as required by Section XI 3.6.2 Minimum Temperature for Mechanical Heatup 164a or Cooldown following Nuclear Shutdown 3.6.3 Minimum Temperature for Core Operation 164b l (Criticality) 3.6.4 Transition Temperature Shift vs. Fluence 164c 6.2-1 Management Organization Chart 244 6.2-2 Organization for Conduct of Plant 245 Operations Amendment No. AM, AR, 46 -iv-4 -o 7-- n. - -,- -, + -+e---- +- - .+-,
7.-._ LIMITING CONDITf0NS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7 CONTAINMENT SYSTEMS 4.7 CONTAINMENT SYSTEMS Applicability: Applicability: Applies to the operating status Applies to the primary and secondary of the crimary and secondary containment integrity. I containment systems. Objective: Objective: To assure the integrity of the To verify the integrity of the primary and secondary containment primary and secondary containment. system. Specification: Specification: A. Primary Containment 1. The suppression chamber water level and temperature shall be t3 1. At any time that the nuclear checked once per day. system is pressurized above Whenever there is indication atmospheric pressure or work 2. a. is being done which has the of reliif valve operation potential to drain the vessel, (except when the reactor is the pressure suppression pool being shutdown and torus cool-water volume and temperature ingisbeingestablished)or shall be maintained within the testing which adds heat to the following limits except as suppression pool, the pool specified in 3.7.A.2. temperature shall be con-tinually monitored and also a. Minimum water volume - observed and logged every 122,900 ft3 5 minutes until the heat b. Maximum water volume - addition is tenninated. 127,300 ft3 3. Whenever there is indication of relief valve operation with the temperature of the suppression pool reaching 160*F or more and the primary coolant system pressure greater than 200 psig, an external visual examination of the suppression chamber shall be conducted before resuming power operation. 4. A visual inspection of the suppression chamber interior, including water line regions, shall be made at each major refueling outage. 165-Amendment No. 46 -.-=.%e-em
...m i PBAPS Unit 3 TAELE 3.7.4 1 PRIMARY CONTAINMENT TESTABLE ISOIATION VALVES i Notes Pen No. 7A AO 80 A; AO 86 A MSIV (1) (2) (3) (5) (9) 7B AO-2-80B ; AO-2-8 6 B 7C AO-2-80C; AO 86 C O 7D AO-2-80D; AO-2-86D V 8 MO-2-7 4 ; MO-2-77 (1) (2) (4) (5) (9) 9A MO 19 ; MO-23-2 0; MO-23-21 [ a 9A MO-2-38A; MO-3663 9B Mo 21 ; MO-13-2 0 ; r MO-13-3 0 ; MO-12-68 ; 9B MO-2-38B; MO-3663 l a 10 MO 15 ; Mo-13-16 i l 11 Mo 15 ; Mo-23-16 ; AO-5 807* a 12 Mo-10-17; MO-10-18 t li 13A MO-10-2SB; Mo 154B; SV-5222 13B MO-10-25A; Mo 154 A; SV-5 221 l 14 MO 15 ; MO 18 l 16A MO-14-12B; MO 11 B; SV-5224 l, 16B MO 12A; MC 11 A ; SV-5225 17 MO 32 ; Mo-10-3 3 t 18 Ao-20-82 ; AC-20-8 3 19 AO-20-94; AO-2 0- 9 5 i
- Effective upon completion of the modification authorized by Amendment No.
Amendment No. 46 -185- .... ~. - _ _ _ _ . _ _.. ~.
1 PBAPS Unit 3 TABLE 3.7.4 (Cont' d. ) PRIMARY CONTAINMENT TESTABLE ISOLATION VALVES, Pen No. Notes 22 AO-3969A; check Valve (1) (2) (4) (5) (10) l 25 AO-3520; AO-3505; AO-3519; (1) (2) (4) (5) (9) l AO-3521A; AO-3521B l 25 AO-3523; Check valves (1) (2) (4) (5) l . 7 V 26 AO-3506; AO-3507 (1) (2) (4) (5) (9) l 26 SV-3671G; SV-3978 G (1) (2) (4) (5) l 26 AO-3509; AO-3510; AO-5235 (1) (2) (4) (5) (9) { 26 SV-5960B; SV-5961B; SV-5966B (1) (2) (4) (5) l 39A MO-10-31B; MO-10-26B (1) (2) (4) (5) (9) 39A SV-5949B; SV-594 8B (1) (2) (4') (5) l 39B MO-10-31A; MO-10-26 A (1) (2) (4) (5) (9) 39B SV-5959A; SV-594 8A (1) (2) (4) (5) j 41 AO-2-39; AO-2-40 (1) (2) (4) (5) (9) 42 check Valve 11-16, XV-14A, XV-143 (1) (2) (4) (5) (10) 51A SV-3671E; SV-3978E (1) (2) (4) (5) l 51B SV-3671D; SV-3978 D l a 51C SV-3671c; SV-3978C l a 51C SV-5960C; SV-5961c; SV-5966C l a 51D SV-39 80 ; Chec k Valve l a 52F AO-3969B; Check Valve (1) (2) (4) (5) (10) { 57 AO-2-316 ; AO-2-317 (1) (2) (4) (5) (9) 203 SV-3671B; SV-39783 (1) (2) (4) (5) l j 20 3 SV-5960D; SV-5961 D; SV-5966D a Amendment No. 46 -186- .-J- - - - - - - - - - - - - - - ^ ^ ^ ^^ ^^ ~
PBAPS Unit 3 TABLE 3.7.4 (cont 8 d.) 1 PRIMARY CONTAINMENT TESTABLE ISOIATION VALVES Pen No. Notes 205A AO-350 2B; Check Valve 9-26B (1) (2) (4) (5) (9) l l -20SB AO-3502A; Check Valve 9-26A 211A MO-10-38B; MO 39B ; MO-10-34B (1) (2) (4) (5) (9) 211A SV-5951B; SV-595 0B (1) (2) (4) (5) l l 211B MO-10-38A; MO 39 A; Mo-10-34A (1) (2) (4) (5) (9) f 211B SV-5951A; SV-5950A (1) (2) (4) (5) l 212 Check valve 13-50; M-524 0; Ao-5241 (1) (2) (4) (5) (9) l 214 Check valve 23-65; AC-5247; Ao-5248 (1) (2) (4) (5) (9) l 217B MO-5 244 ; Mo-5244A (1) (2) (4) (5) (9) l: 218A AO-3968 (1) (2) (4) (5) (10) l 218B SV-3671A; SV-3978 A (1) (2) (4) (5) l 219 Ao-3511; M-3 512 ; Ao-3513; Ao-3514 (1) (2) (4) (5) (9) [ 219 SV-3671F; SV-3978 F; SV-5960A (1) (2) (4) (5) l SV-5961A; SV-5966A l 221 Check Valve 13-38 (1) (2) (4) (5) (9) 223 Check Valve 23-56 (1) (2) (4) (5) (9) 225 Mo 41 ; MO-13-3 9 (1) (2) (4) (5) (9) 225 MO 70 ; MO-14-71 (1) (2) (4) (5) (9) 227 Mo-23-58; MO-23-57 (1) (2) (4) (5) (9) Amendment No. 46 -187-W'N-*New .m.g a
A, I ?A .. ~. -= l PBAPS i 3.7.A & 4.7.A BASES s.at'd). t The maximum allowable volume assures the integrity and functional capability of the Suppression Chamber (torus) during postulated LOCA pool swell effects on the torus support system. The majority of the Bodega tests were run with a sub-merged length of 4 feet and with complete condensation. Thus, with respect to downcomer submergence, this specification is adequate. The maximum tempera-ture at the end of blowdown tested during the Humboldt Bay and Bodega Bay tests was 170*F and this is conservatively taken to be the limit for complete con-densation of the reactor coolant, although condensation would occur for temp 2ratures above 170"F. Should it be necessary to drain the suppression chamber, this should only be i dann when there is no requirement for core standby cooling systems operability as explained in basis 3.5.F. Er 'rimental data indicates that excessive steam condensing loads can be avoided 11...he peak temperature of the suppression pool is maintained below 160*F dur-ing any period of relief valve operation with sonic conditions at the discharge
- exit. Specifications have been placed on the envelope of reactor operating conditions so that the reactor can be repressurized in a timely manner to avoid tha regime of potentially high suppression chamber loadings.
Btcause of the large volume and thermal capacity of the suppression pool, the volume and temperature changes very slowly and monitoring these parameters daily is sufficient to establish any temperature trends. By requiring the suppression pool temperature to be continually monitored and frequently logged during periods of testing which add significant heat, the temperature trends will be closely followed so that appropriate action can be taken if required. Logging is not required during inadvertent relief valve operation since during such periods operator action is actively and directly involved in cperations i relating to controlling torus temperature and monitoring of temperature trends is a natural part of the operations. Additionally torus temperature is monitored b) recorder during these periods so that an historical record is available. Operating procedures define the action to be taken in the event a relief valve inadvertently opens or sticks open. As a minimum this action shall include: (1) use of all available means to close the valve, (2) initiate suppression pool water cooling heat exchangers, (3) initiate reactor shutdown, and (4) if oth2r relief valves are used to depressurize the reactor, their discharge shall be separated from that of the stuck-open relief valve to assure mixing and uniformity of energy insertion to the pool. The requirement for an external visual examination following any event where potentially high loadings could occur provides assurance that no sipificant damage was encountered. Particular attention shwld be focused on struci.w al discontinuities in the vicinity of the relief valve discharge since these are expected to be the points of highest stress. I Amendment No 46 -190-p, -o e - - = - -e f, - - - - - - - - - - - - - ~ - -
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