ML18086B361
| ML18086B361 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 02/23/1982 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Robert E. Uhrig FLORIDA POWER & LIGHT CO. |
| References | |
| TASK-2.B.1, TASK-TM NUDOCS 8203120346 | |
| Download: ML18086B361 (6) | |
Text
Docket Nos. 50-272 and 50-311 Mr. R. A. Uderitz Vice President - Nuclear Public Service Electric and Gas Mai l Code Tl 5A P.O. Box 570 Newark, New Jersey 07101
Dear Mr. Uderitz:
FEB 2 3 1982 DISTRIBUTION Dockets NRC PDR L PDR TERA MSIC ORB#l Rdg DEisenhut OELD IE ACRS-10 Gray File CParrish JHannon WRoss
SUBJECT:
REACTOR COOLANT SYSTEM VENTS, (ITEM I I.B.1)
REQUEST FOR ADDITIONAL INFORMATION l~e have completed a preliminary review of your sul:mitta1 s regarding TMI Action Plan Item II.B.l, RCS High Point Vents.
The additional information identified in the enclosur-e is-required to compa:ete our review for Salem Units l and 2.
We are currently in the process of reviewing the technical merit of the proposed operating guidelines 1fi'or RCS Vent usage.
We recommend that the questions in this area be resolved generically through the Owners Groups.
Specific plant procedures will be reviewed against the approved guidelines as needed in the future; but not necessarily prior to design approval.
Please supply the requested information within 60 days of the date of this 1 etter.
The reporting and/or recordkeeping requirements contained in this letter are approved under OMB clearance #31:50-0065 which expires May 31, 1983.
Enclosure:
Request for additional in format ion cc w/enclosure:
See next page OFFICE *
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! 8203120346 820223 NAO PDR ADOCK 05000272
_" : PDR Sincerely,
- O*riginal signed by~*
- s. A. Varga Steven A. Varga, Chief Operating Reactors Branch #1 Division of Licensing
>FFICIAL REGOR D COPY USGPO: 1981-335-960
Mr. R. A. Uderitz Public Service Electric and Gas Company cc: Mark*J. Wetterhahn, Esquire Conner and Wetterhahn 1747 Pennsylvania Avenue, NW Suite 1050 Washington, D.C.
20006 Richard Fryling, Jr., Esquire Assistant General Solicitor Public Service Electric and Gas Company Mail Code TSE - P.O. Box 570 Newark, New Jersey 07101 Gene Fisher, Bureau of Chief Bureau of Radiation Protection 380 Scotch Road Trenton, New Jersey 08628 Mr. R. L. Mittl, General Manager -
Corporate Quality Assurance Public Service Electric and Gas Company Mail Code Tl6D - P.O. Box 570 Newark, New Jersey 07101 Mr. Henry J. Midura, General Manager -
Salem Operations Public Service Electric and Gas Company P.O. Box 168 Hancocks--Bridge, New Jersey 08038 Salem Free Library 112 West Broadway Salem, New Jersey 08079 Leif J. Norrholm, Resident Inspector Salem Nucl.ear Generating Station U. S. Nuclear Regulatory Commission Drawer I Hancocks Bridge, New Jersey 08038 Mr. Edwin A. Liden, Manager -
Nuclear Licensing Public Service Electric and Gas Company Mail Code Tl6D - P.O. Box 570 Newark, New Jersey 07101 Ronald C. Haynes Regional Administrator - Region I U. S. Nuclear Regulatory Conmission 631 Park Avenue King of Prussia, Pennsylvania 19406
REQUEST FOR ADDITIONAL INFORMATION FOR SALEM I & 2 I~ Your submittal of June 30, 1981 contained information concerning only the reactor vessel head vent.
Provide information on the means for venting the pressurizer (reference NUREG-0737 Item 11.B. I Clarification C.(3)). Include a description of the pressurizer* vent and its instrumentation, power and contro.1 system, appropriate drawings (with a legend of symbols and abbreviations), and a discussion of the pressurizer vent design with respect to each point of clarification of NUREG-0737 Item 11.B. I.
- 2.
In addition to the generic guidelines for operation. of the reactor vessel head vent provided as part of your response to NUREG-0737 Item 11.B. I, provide the following additional information:
- a. Procedural guidelines, similar to the previously submitted reactor vessel head vent guidelines, for venting of the pressurizer (references NUREG-0737 Item 11.B. I Position (2) and Clarification A.(2)).
- b.
Procedural guidelines which in lieu of venting will assure that sufficient liquid or steam will flow through the steam generator U-tube region so that decay heat can be effectively removed from the reactor coolant system (reference NUREG-0737 Item 11.B. I Clarification C.(2)).
- 3. Demonstrate that the reactor vessel head vent and pressurizer vent are sized adequately to perform their safety-related function by stating the vent flow rate and the design criteria for vent sizing (reference NUREG-0737 Item 11.B.1 Clarificat.ion A.(3)).
i
- 4. The following items apply to the portions of_ the reactor vessel head vent and pressurizer vent that fo~m ~part of the reactor coolant pressure boundary, up to and including the second normally closed valve or safety/relief valve (reference NUREG-0737 Item 11.B. I Clarification A.(7)):
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- a.
Verify that the piping, valves, and components (and supports for the pressurizer vent) are classified Seismic Category I and Safety Class 2 (Safety Class I where the size corresponds to the 10 CFR Part 50 Appendix A definition of a loss-of-coolant accident).
- b.
Provide the design temperature and pressure of the piping, valves, and components.
- c. Describe the instrumentation that has been provided to detect and measure pr~ssurizer and reactor vessel head vent isolation valve leakage {reference Appendix A to 10 CFR Part 50, General Design Criterion 30).
- d.
Verify that the materials of construction will be fabricated and tested in accordance with SRP Section 5.2.3, "Reactor Coolant Pressure Boundary Materials."
- e. Demonstrate that internal missiles and the dynamic effects associated with the postulated rupture of piping will not prevent the essential operai:on of the vent system {i.e., at least one vent path remains functional) {reference Appendix A to 10 CFR Part 50, General Design Criterion 4).
- 5. Verify that the following reactor vessel head and pressurizer vent failures have been analyzed and found not to prevent the essential operation of safety-related systems required for safe reactor shutdown or mitigation of the consequences of a design basis accident:
- a.
- b.
Seismic failure of any pressurizer vent components that are not designed to withstand the safe shutdown earthquake.
Postulated missiles generated by failure of reactor vessel head and pressurizer vent components.
Dynamic effects associated with the postulated rupture of pressurizer vent piping greater than one-inch.nominal size.
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- d.
Fluid sprays from reactor vessel head and pressurizer vent component failures.
Sprays from normally unpressurized portions of the vents that are Seismic Category I and Safety Class I, 2, or 3 and have instrumentation for detection of leakage from upstream* isolation valves need not be considered.
- 6.
Provide a reliability analysis consisting of a faill!re mode and effects analysis (FMEA) or equivalent qualitative analysis for the pressur!zer vent path that shows that no single active component failure, human error, or test and maintenance action could result in inadvertent opening or failure to close ofter intentional opening *.
Include in the analysis components in the associated power, instrumentation, and control systems as well as the electrical and mechanical components of the pressurizer vent system (reference NUREG-0737 Item 11.B. I Clarifications A.{7) and (8)).
- 7.
Your submittal of June 30, 1981 stated that the reactor vessel head vent has the potential of venting to containment, but the only route shown is through the pressurizer relief tank rupture disc.
Verify that the rupture disc is the vent to containment, or provide additional information on the vent path* to containment.
Also~ demonstrate that both the reactor vessel head and pressurizer v.. 1t paths to the containment atmosphere discharge into areas:
- a. That provide good mixing with containment air to prevent the accumulation or pocketing of high concentrations of hydrogen, and
- b.
In which any nearby structures, systems, and components essential to safe shutdown of the reactor or mitigation of a _design basis accident are capable of withstanding the effects of the anticipated mixtures of steam, liquid, and noncondensible gas discharging from the RCS vents (reference NUREG-0737 Item 11.B. I Clarification A.(9)).
- 8.
Verify that operability testing of the reactor vessel head and pressurizer vent valves will be performed in accordance w'ith subsection IWV of Section XI of the ASME Code for Category B valves (reference NUREG-0737 Item 11.B.1 Clarification A.( I I)).
- Page 3 of 4
- 9.
Verify that all displays (including alarms) and controls, added to the control room as a result of the TMI Action Plan requirement for reactor coolant system vents, have been or will be considered in the human factors analysis required by NUREG-0737 Item l.D. I, "Control-Room Design Reviews."
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