ML19343B745
| ML19343B745 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/17/1980 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19343B741 | List: |
| References | |
| NUDOCS 8012300199 | |
| Download: ML19343B745 (6) | |
Text
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4' 2.0 SAFETY LIMITS 2.1 SAFETY tIMITS REACTOR C00LANT SYSTEM PRESSURE 2.1.3 Not applicable.
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i il1[- {,'f EIIL' 2.1 SAFETY LIMITS i
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2.1.3 REACTOR COOLANT SYSTEM PRESSURE 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 be 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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.a LIMITING CONDITIONS FOR OPERATION REMOTE SHUTDOWN INSTRUMENTATION 3.3.3.5 The remote shutdown monitoring instrumentation channels shown in Table 3.3-9 shall be OPERABLE with readouts displayed external to the control room.
APPLICABILITY:
RECOVERY MODE.
ACTION:
With the number of OPERABLE remote shutdown monitoring channels less than required bj Table 3.3-9, notify the hRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and restore the inoperable channel to OPERABLE status within 30 days.
l POST-ACCIDENT INSTRUMENTATION 3.3.3.6 The post accident monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE.
APPLICAElllli:
RECOVERY MODE.
ACTION:
With the nue er of OPERAELE post-accident monitoring channels less than required 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 />.
CHLORINE DETECTION SYSTEMS 3.3.3.7 Two chlorine detection systems, with their alarm / trip setpoints adjusted to actuate at a chlorine concentration of less than or equal to 5 ppm, shall be OPERABLE:
One at the air intake tunnel, and a.
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 mode of operation; restore the inoperable detection system to OPERABLE status within 30 days.
THREE MILE ISLAND - UNIT 2 3.3-7 W-
i.17@..O 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 pursuant 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:
REC 0VERf 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 280 F and at a pressure of less than 600 psig.
avg 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.
"The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.
lHREE MILE ISLAND - UNIT 2 3.4-1 e
ADMINISTRATIVE CONTROLS SPECIAL RE)0RTS' 6.9.2 Special 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:
Records of sealed source and fission detector leak tests and results, a.
b.
Records of annual physical inventory of all sealed source material of record.
Records of changes made to the procedures required by Specifications c.
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, Records and logs of unit operation covering time interval at each a.
powcr 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 systehis, c.
ALL REPORTABLE OCCURRENCES submitted to the Commission.
d.
Records of surveillance activities, inspections and calibrations required by these Technical Specifications.
Records of changes made to the procedures required by Specifications e.
6.8.1 a.,
b.,
c., f. and g.
f.
Reports required by 6.9.1.6 and 6.9.1.10.
g.
Records of radioactive shipments.
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 Report.
j.
Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
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Records of transient or operational cycles for those unit components designed for a limited number of transients or cycles.
1.
Records of reactor tests and experiments.
i Records of training and qualification for current members of the m.
unit staff.
Records of in-service inspections performed pursuant to these n.
Technical Specifications.
Records of Quality Assurance activities required by the Operating o.
Quality Assurance Plan.
p.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
q.
Records of meetings of the PORC and the GRC.
r.
Records of the incident which occurred on March 28, 1979.
Records of unit radiation and contamination surveys.
s.
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Records of radiation exposure for all individuals entering radiation control areas.
Records of gaseous and liquid radioactive material released to the u.
t environs.
6.11 RADIATION PROTECTION PROGRAM Personnel radiation protection shall be consistent with the requirements of 10 CFR Part 20 and the NRC approved Radiation Protection Plan.
6.12 HIGH RADIATION AREA In lieu of the " control device" or " alarm signal" required by paragraph J
20.203(c)(2) of 10 CFR 20, each high radiation area shall be controlled as specified in the Radiation Protection Plan.
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