ML20154L370: Difference between revisions

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{{Adams
#REDIRECT [[HBL-88-047, Replacement Pages for Proposed Safstor Tech Specs,Rev 0]]
| number = ML20154L370
| issue date = 05/23/1988
| title = Replacement Pages for Proposed Safstor Tech Specs,Rev 0
| author name =
| author affiliation = PACIFIC GAS & ELECTRIC CO.
| addressee name =
| addressee affiliation =
| docket = 05000133
| license number =
| contact person =
| document report number = HBL-88-047, HBL-88-47, NUDOCS 8805310264
| package number = ML20154L343
| document type = TECHNICAL SPECIFICATIONS, TECHNICAL SPECIFICATIONS & TEST REPORTS
| page count = 7
}}
 
=Text=
{{#Wiki_filter:-
    ,,                                                  PG&E Letter No. HBL-88-047 ENCLOSURE 2 REPLACEMENT PAGES FOR PROPOSED SAFSTOR TECHNICAL SPECIFICATIONS, REVISION O 8805310264 880523 PDR    ADOCK 05000133 P                DCD 2107S/0059K
 
TABLE III-2 LIMITS FOR SPENT FUEL STORAGE POOL HATER CHEMISTRY AND ACTIVITY DURING SAFSTOR Parameter                                              Limits (a)
: 1. pH                                              5.3 to 6.5
: 2. Chlorides (b)                                  0.5 ppm (maximum)
: 3. Conductivity                                  10.0 pmho/cm (maximum)
: 4. Cs-137 activity (c)                            1.0 x 10-4 pCi/ml (maximum)
(a) Verification shall be accomplished by analysis of samples taken at least once each month.
(b) Chloride analysis is required only if conductivity exceeds 2.0 pmho/cm (Reference NRC Regulatory Guide 1.56, figure 2).
(c)  By gamma spectrometry.
21075/0059K                            III - 5                            Revision 0
 
o V. MONITORING SYSTEMS A. DESIGN FEATURES
: 1. Stack Gas Monitorina System A system shall be provided to determine routine releases of particulate radioactivity and to provide monitoring and annunciation of nonroutine releases of radioactive noble gases. The stack gas monitoring system shall consist of a particulate filter holder, a beta-sensitive detector system, and a sample pump to produce a sample flow controlled at approximately 2 cfm. The particulate filters shall be removed for laboratory counting. The detector system shall have two detectors (one as an operating spare) to respond to radioactive (beta-emitting) gases that pass through the system. The detector system shall be designed to be sensitive to Kr-85 in the stack gas from approximately 5 x 10-7 to approximately 2 x 10-2 C1/cc.
: 2. Process Water Monitor l                      A process water radiation monitoring system employing a gamma-sensitive scintillation detector shall be provided to l
indicate, record, and annunciate high radiation levels in the radwaste discharge line to the circulating water system. The range of the monitor shall be from 10 to 10 6cpm with a typical f
2107S/0059K                          V-1                            Revision 0 l
t
: c. The stack particulate filter will be removed for laboratory counting weekly.
: d. The vent header that collects all vents from the liquid radwaste treatment facility shall be connected to the plant ventilation exhaust system to permit monitoring by the stack gas monitoring system.
: 2. Process Hater Monitor
: a. The monitor shall normally be OPERABLE to detect inadvertent discharge of radwaste. It may be taken out of service for calibration and maintenance but shall be returned to service as soon as practicable. When the monitor is out of service, any release shall be verified by analysis of duplicate independent samples and independent verification of the valve lineup before the activity is released.
: b. The monitor shall be source-checked quarterly and shall be calibrated annually. The monitor shall be set to alarm at or below a Cs-137 concentration in the discharge line of 1 x 10-4 pCi/ml. Alarm functions and background readings shall be checked weekly. If a background reading exceeds the equivalent of 5 x 10-5 pCi/m1, the cause will be investigated and remedial measures taken to reduce the background reading.
2107S/0059K                          V-5                                Revision 0
: b. Each sealed source shall be tested for leakage and contamination by the licensee or other persons specifically authorized by the Commission or an Agreement State. The test method shall have a detection sensitivity of at least 0.005 pCi.
: c. Each sealed source described in a. above (excluding startup sources and fission detectors previously subject to core flux) shall be tested for leakage and contamination as follows:
(1) Sources in Use - At least once per 6 months for all sources containing radioactive material, other than hydrogen 3, with a half-life greater than 30 days and in any form other than gas.
(2) Stored Sources Not in Use - Each sealed source and fission detector shall be tested prior to use or transfer to another licensee unless tested within the previous 6 months. Sealed sources and fission detectors transferred without a certificate indicating the last test date shall be tested prior to being placed into use.
21075/0059K                          V - 10                            Revision 0
 
TABLE V-1 OPERATING LIMITS FOR GROUNDHATER ACTIVITY DURING SAFSTOR Parameter                                    Limit                          Basis Gross alpha                                  15 pCi/1                      Drinking water standard Gross beta                                    50 pCi/1                      Drinking water standard Tritium                                      3 x 10-5 pCi/mi                1% of 10 CFP. 20, Appendix B Table II, Column 2 Gamma emitters                                                          --- 1% of 10 CFR 20, Appendix B, Table II, Column 2 for individual isotopes l
l 21075/0059K                                                                  V - 11                        R6sision 0
 
  *.    ..                                                                                      1
: g. Surveillance activities required to demonstrate compliance with the Technical Specifications
: h. Calibration of instrumentation used to demonstrate compliance with Technical Specifications
: 1. Shipping and disposal of radioactive materials
: 2. Procedure Review All procedures described in item 1 above, and changes thereto, shall be reviewed by the PSRC and approved by the Plant Manager prior to implementation, except as provided in items 3 and 4 below.
: 3. Procedure Chances Rules shall be established that provide methods by which temporary changes can be made to approved procedures, including the designation of those persons authorized to approve such changes. Temporary changes that clearly do not change the intent of the approved precedure from the standpoint of nuclear safety may be approved by two members of the plant management staff, at least one of whom is a Certified Fuel Handler. Such changes shall be documented and, if appropriate, incorporated into the next revision of the affected procedure.
2107S/0059K                          VII - 21                          Revision 0
                                                                                                ,}}

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