ML20004A066
| ML20004A066 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/28/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20004A053 | List: |
| References | |
| NUDOCS 8105110638 | |
| Download: ML20004A066 (8) | |
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.ACILITY OPERATING LICENSE NO. CPR-73 DOCKET NO. 50-320 Replace the folicwing pages of the proposed Appendix "A" Technical Specifications with the enclosed pages as indicated.
The revised pages contain vertical lines indicating the area of change. The corresponding overleaf pages are also pro-vided to maintain document completeness.
Pages 2-1 32-1 3.3-7 3.4-1 6-15 6-16 l
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d 2.0 SAFETY LIMITS 2.1 SAFETY LIMITS REACTOR COOLANT SYSTEM PRESSURE 2.1.,3 Not applicable.
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THREE MILE ISLAND - UNIT 2 2-1
2.1 SAFETY LIMITS BASES 2.1.3 REACTOR COOLANT SYSTEM PRESSURE P
As a result of the March 28, 1979 accident, the pressure retaining ability of the reactor coolant system is uncertain. Therefore, a meaningful reactor coolant system pressure Safety Limit can not ce established.
However, the reactor coolant system pressure has been reduced to approximately 90 psig.
Furthermore, since Technical Specification 3.4.9.1 establishes 600 psig as a Limiting Condition for Operation for the reactor coolant system, no further limitations are required.
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THREE MILE ISLAND - UNIT 2 B 2-1
oo LIMITING CONDITIONS FOR OPERATION REMOTE SHDTDChN INSTRUMENTATION 3.3.3.5 The remote shutdown monitoring instrumentation channels shown in Table 3.3-9 shall be OPERABLE with readcuts displayed external tc the control room.
APPLICABILITY:
RECOVERY MODE.
ACTION:
With the number of OPERABLE remote shutdown sonitoring channels less than required by Table 3.3-9, notify the NRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and restore the l
inoperable channel to OPERABLE status within 30 days.
POST-ACCIDENT INSTRUPENTATION 3.3.3.6 The post-accident monitoring instrumentation channel.1 shown in Table 3.3-10 shall be OPERABLE.
APPLICABILITY:
RECOVERY MODE.
ACTION:
With the number of OPERABLE post-accident monitoring channels less than recuired by Table 3.3-10, restore the inoperable channel (s) to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
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CHLORINE DETECTION SYSTEMS l
3.3.3.7 Two chlorine detection systems, with their alarn/ trip setpoints adjusted to actuate at a chlorine concentration of less than or equal to 5 ppm, shall be OPERABLE:
a.
One at the air intake turnel, and b.
One at the control room air supply duct.
APPLICABILITY:
RECOVERY MODE.
ACTION:
With one or more chlorine detection systems inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate and maintain operation of the control room emergency ventilation system in the recirculation sede of operation; restore the inoperable detection system to OPERABLE status within 30 days.
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l THREE MILE ISLAND - UNIT 2 3.3-7
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s ADMINISTRATIVE CONTROLS SPECIAL REPORTS 6.9.2 Speg'll reports shall be submitted to the Director of the Office of Inspection and Enforcement Regional Office within the time period specified for each report.
6.10 RECORD RETENTION 6.10.1 The following records shall be retained for at least five years:
a.
Records of sealed source and fission detector leak tests and results.
b.
Records of annual physical inventory of all sealed source material of record.
c.
Records of changes made to the procedures required by Specifications 6.8.1 d. and e.
6.10.2 The following records shall be retained as long as the Licensee has an NRC license to operate or possess the Three Mile Island facility.
a.
Records and logs of unit operation covering time interval at each pcwer level.
b.
Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety and radioactive waste systems.
c.
ALL REPORTABLE OCCURRENCES submitted to the Commission.
d.
Records of surveillance activities, inspections and calibrations required by these Technical Specifications.
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Records of changes made to the procedures required by Specifications 6.8.1 a.,
b.,
c.,
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f.
Reports required by 6.9.1.5 and 6.9.1.10.
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Records of radioactive shipments.
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h.
Records and logs of radioactive waste systems operations.
i.
Records and drawing changes reflecting facility design modifications made to systems and equipment described in the Safety Analysis l
Report.
j.
Records of new and irradiated fuel inventory, fuel transfers and assemoly burnup histories.
I THREE MILE ISLAND - UNIT 2 6-15 l
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LIMITING CONDITIONS FOR OPERATION 3.4 REACTOR COOLANT SYSTEM REACTOR COOLANT LOOPS 3.4.1 The Reactor Coolant System shall be operated in accordance with procedures approved oursuant to Specification 6.8.2.
APPLICABILITY:
RECOVERY MODE.
ACTION:
None except as provided in Specification 3.0.3.
SAFETY VALVES 3.4.3 All pressurizer code safety valves shall be OPERABLE with a lift setting of 2435 PSIG + 1%.*
APPLICABILITY:
RECOVERY MODE.
ACTION:
None except as provided in Specification 3.0.3.
3.4.9 PRESSURE / TEMPERATURE LIMITS REACTOR COOLANT SYSTEM 3.4.9.1 The Reactor Coolant System shall be maintained at a T of less than avg 280 F and at a pressure of less than 500 psig.
APPLICABILITY:
When fuel is in the reactor pressure vessel.
ACTION:
With the Reactor Coolant System pressure exceeding 600 psig, immediately reduce the Reactor Coolant System pressure to within its limit.
"Tne lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.
THREE MILE ISLAND - UNIT 2 3.4-1
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UNITED STATE 5 0.: AMERICA APR 101981
- NUCLEAR REGULATORY CCMMISSICN H
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3E:0RE THE ATCM.IC SAFE f AND LICENSINr 30ARD x
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METROPOLITAN EDISCN COM;ANY, et al.
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Occket Nc. 50-320 OLA O l$f7
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(Three Mile Island Nuclear Statien,
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April 3, 1981 4 2) h ORDER GRANTING JOINT MO~!CN 44 TO AP: ROVE STI?ULATICN
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,19El, this At:mic Safety and Licensine Scard was sened 3
Ocin: Motien filed by several parties :: the ca::icnad pr:ceecing z
re:uesting a;;r: val f the "Sti:ulatien Regarding Se::lement Of Issues" attacned there::. Ac::rcing := the Ocin: Metien, the subject stipula:icn was enterad int: by Intervencrs Steven Shelly and William L chstet, the i
NRC 5taff and the Lictenses fer the pur;cse of res:1ving all cf tne issues acvanced by Mr. ShcIly and cne Of the issues advanced by Mr. L:chstet relative to tais pr ceeding. Tne stipulaticn c:ntains the basis up:n wnich an agree-ment was reached ameng the parties by which the issues in uestien are deemed se:: led.
Tne Licensing 5 card regards the Jcint K::icn and subjec Sti:ulaticn as furthering the principles of settlement and c:m:r: mise Of NRC litigatien.
Ac::rdingly, it is hereby CRCERED that:
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_2 The hein: Mc:icn is granted; 1.
2.
The "Reques: for Hearing" cf Steven C. Shelly dated March 21, 1930, and supplement there:c, dated June 19, 1980, are deemed withdrawn and Mr. ShcIly thereby dismissed frem the proceeding; 3.
Pro;csed atentien 1 contained in the supplemen to the recuest for hearing of Mr. William Lochstet, dated June 17,195C, is deemed witndrawn; and 4
Prc: sed Techni:31 Scecificatiens 2.1.3, 3.3.3.5, 3.4.9.1, 6.10.1, and 5.10.2 set forth in an attachment to tne February 11,1930 Crder issued :y the Direc :r, Nuclear Rea:::r Regulati:n, snall be =cdified in accordance with the revisiens s:ecified in the ;r :csed Acenc=en:
Of Order attached to the " Stipulation Regarding Settlemer.: cf Issues" upcn entry of that Amendment cf Order.
FOR THE ATCMIC SAFETY AND LICEN5!N1 3CAE0 c:L_,
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Jchn F. Welf, Esc., Chairman i
Cated at Bethesda, Maryland
- nis 9tn :ay of Acril, 1981.
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