ML18082A323
| ML18082A323 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 04/11/1980 |
| From: | Ross W Office of Nuclear Reactor Regulation |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8005080252 | |
| Download: ML18082A323 (5) | |
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§ 005 0 8 0 2..-52, APRIL l 1 l900 Mark J. Wetterhahn, Esquire Conner, Moore and Corber Suite 1050 1747 Pennsylvania AverrJe, NW Washington, O. C.
20006 Richard Fryling, Jr., Esquire Assistant General Solicitor Public Service Electric and Gas Company 80 Park Place Newark, New Jersey 07101 Gene Fisher, Bureau of Chief Bureau of Radiation Protection 380 Scotch Road Trenton, New Jersey 03628 Mr. Hank Midura, Manaser Salem Nuclear Generating Station Public Service Electric and Gas Company BO Park Pl ace Newark, New Jersey 07101 Mr. R. L. Mittl,.General Manager Licensing and Environr:ent Public Service Electric and Gas Company 80 Park Place Newark, New Jersey 07101 Salem Free Library 112 West Broadway Salem. New Jersey 08079 Leif J. Norrholm, Resident Inspector Salem Nuclear Generating Station U. s. Nuclear RegJlatcry Corrrnission Dra\\'1er I Hancocks Bridge, :'le?! Jersey 08038
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 APRIL l 1 1980 MEMORANDUM FOR:
A. Schwencer, Chief, Operating Reactors Branch #1, DOR FROM:
W. J. Ross, Project Manager, Operating Reactors Branch #1, DOR
SUBJECT:
SUMMARY
OF MARCH 19, 1980 MEETING WITH PUBLIC SERVICE ELECTRIC AND GAS COMPANY RELATED TO IMPLEMENTATION OF APPENDIX I FOR SALEM UNIT NO. 1 On March 19, 1980, the staff met with representatives. of the licensee to discuss the licensee's proposed Radiological Effluent Technical Specifications (RETS) for Salem, Unit No. 1.
A list of participants is attached.
The agenda for the meeting included the following:
A.
Description of the Site Process Control Program (PCP)
B.
Development of an Offsite Dose Calculation Manual (ODCM)
C.
Discussion of Proposed RETS.
A.
PCP - The licensee's representatives presented a general description of the systems and procedures used to isolate, sample, and package solid wastes with emphasis on spent resins.
The staff found this description to be adequate, but suggested the PCP be revised based on recommendations that:
- 1.
The licensee document the initial test efficiency of the resin dewatering process (12-hour standing period, plus) and strive for removal of water to the greatest possible extent.
The staff must be assur~d that the liquid content of solid wastes will meet the require-ments of the burial sites.
- 2.
The PCP should address the use and care of hoses.
- 3.
The PCP should specify the ccntai~er description and qualifications.
- 4.
The PCP should address the use of any containers (including those of 300 it 3 c2p2city) and describe how the water in these containers is measured.
- 5.
The"PCP should provide the method for calculating total curie con-tent per container and describe the sampling means to determine radionucl~des.
I~
A. Schwencer 2
APRIL 1 1980 The staff discussed the dewatered resin operations and indicated that the proposed PCP is subject to burial site requirements and that the RETS provides a means to change the PCP.
- 8.
ODCM - The staff had reviewed this document and requested additional information in two areas:
- 1.
In Section 4.4 the ODCM states that the Jiquid radwaste system will be operated if 11 during any calendar quarter the whole body or organ dose exceeds 0.375 mrem or 1.25 mrem respectively.
11 Similarly, Section 6.5.1 states that the gaseous radwaste treatment system shall be operated 11 if the calculated dose exceeds 1.25 mrad for gamma radiation and 2.5 mrad for beta radiation during any calendar quarter.
11 At the staff's request, the licensee will revise the ODCM to show what methodology will be used to satisfy RETS Specifications 3.11.1.3 and 3.11.2.4.
- 2.
The licensee will review Table 5.1 on Page 6.7 to assure that the data in the second column refers to particulates.
The staff found Section 3 for the alarm/setpoints to be acceptable; how~ver, not all of the radiation monitors listed in the RETS were included in the ODCM and should be added in a revision.
The ODCM should also include the method of mixing stored liquids prior to representative sampling per RETS Specification 4.11.1.1, Table 4.11-1, footnoted.
C.
RETS - At the conclusion of a review of these RETS, the following general items are considered to be open:
Page 3/4 12 Staff will review frequencies for performing analyses for the radiological monitoring program.
Page 5 The staff will determine if the workers at the Hope Creek construction site should be categorized as 11 the public.
The following specific items remain open:
Table 3.3-11, Page 3/4 3 Licensee advised the staff that there is not a flow switch on the circulating water pump for assuring minimum dilution flow.
Licensee controls administratively.
Licensee will determine if an interlock is needed.
Table 3.3-12, Page 3/4 3 Licensee has only one oxygen monitor for the waste gas/combustible gas monitoring system.
The specifica-tions and the ETSB Branch Position require dual oxygen monitors.
The licensee should consider a second monitor.
Without the second monitor, Table 3.3.12 Action 40 would require hot standby conditions within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> if the single monitor is inoperable.
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A. Schwencer 3
.'.\\PR IL l 1 net Table 4.3-8, Page 3/4 3-61 (4E) - Staff will review licensee's contention that acquisition of data from a rotometer 90 ft off the ground is a safety problem.
Table 4.3-8, Page 3/4 3 Licensee advises that oxygen meter cannot measure oxygen below 2 volume percent.
Staff approved calibration with 2% and 4% oxygen.
3/4 11.l Page 3/4 11 Following the_meeting, the staff provided the basis for the limitation of 2 x 10 4 µCi/ml dissolved or entrained noble gases that may be released from the site to unrestricted areas.
4.11. 1.1.2, Page 3/4 11 Licensee will review its procedures to assure the concentrations of radioactive materials are maintained within the limits required by 3.11.1.1.
Table 4.11-1, Page 3/4 11 Licensee will provide a sketch 6f piping associated with releases via steam generator blowdown and from the chemical waste basin as well as via turbine building liquid pathways.
Table 4.11-1, Page 3/4 11-3a - Licensee will review the reason that the sensitivity of measurements is based on the MDA (Maximum Detectable Activity) rather than on the LLD (Lower Limit of Detection).
Table 4.11-2, Page 3/4 11 LLD should b~ labelled as µCi rather than mCi.
The frequencies of sampling in Notes 11 b 11 11 d 11
, and 11 e 11 remain open items to be resolved by the staff and licensee.
3.11.2.5, Page 3/4 11-18 Licensee will review Action Item 11 b 11 to determine if it can be performed.
Section 6 - Discussion of this section was postponed.
- '~. )u.~* J.. L
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w: J.
oss, Project Manager Operating Reactors Branch #1
.Division of Operating Reactors
Participants NRC PSE&G
- w. J. Ross T. w. Bannoy M. Fl iegel N. L. Mi 11 is H. Krug N. c. Allman J. s. Boegli