ML14183A697
| ML14183A697 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 10/13/1995 |
| From: | Mozafari B NRC (Affiliation Not Assigned) |
| To: | Hinnant C CAROLINA POWER & LIGHT CO. |
| References | |
| TAC-M93569, NUDOCS 9510200380 | |
| Download: ML14183A697 (4) | |
Text
October 13, 1995 Mr. C. S. Hinnant, Vice President Carolina Power & Light Company H. B. Robinson Steam Electric Plant, Unit No. 2 3581 West Entrance Road Hartsville, South Carolina 29550
SUBJECT:
CHANGE TO TECHNICAL SPECIFICATION BASIS SECTION 4.4.1.2 ON THE OPERATION OF THE CONTAINMENT PENETRATION PRESSURIZATION SYSTEM FOR THE H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 (TAC NO. M93569)
Dear Mr. Hinnant:
By letter dated July 28, 1995, Carolina Power & Light Company (CP&L) proposed a change to the H. B. Robinson Steam Electric Plant, Unit No. 2 (HBR),
Technical Specifications (TS) Basis section 4.4.1. The Basis change clarifies that the penetration pressurization system (PPS) may be used in either the continuous or intermittent mode, which is consistent with TS section 4.4.1.2.a and 10 CFR 50, Appendix J, "Primary Reactor Leakage Testing for Water-Cooled Power Reactors."
The NRC staff has reviewed the proposed basis change regarding the operation of the PPS and has no objection to your proposed change.
Enclosed is a copy of the revised Basis page.
Sincerely, (Original Signed By)
Brenda Mozafari, Project Manager Project Directorate II-1 Division of Reactor Projects -
I/II Office of Nuclear Reactor Regulation Docket No. 50-261 Distribution Docket File DVerrelli, RII
Enclosure:
Basis page 4.4-10 PUBLIC PD2-1 RF cc w/enclosure:
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-W001 October 13, 1995 Mr. C. S. Hinnant, Vice President Carolina Power & Light Company H. B. Robinson Steam Electric Plant, Unit No. 2 3581 West Entrance Road Hartsville, South Carolina 29550
SUBJECT:
CHANGE TO TECHNICAL SPECIFICATION BASIS SECTION 4.4.1.2 ON THE OPERATION OF THE CONTAINMENT PENETRATION PRESSURIZATION SYSTEM FOR THE H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2'(TAC NO. M93569)
Dear Mr. Hinnant:
By letter dated July 28, 1995, Carolina Power & Light Company (CP&L) proposed a change to the H. B. Robinson Steam Electric Plant, Unit No. 2 (HBR),
Technical Specifications (TS) Basis section 4.4.1. The Basis change clarifies that the penetration pressurization system (PPS) may be used in either the continuous or intermittent mode, which is consistent with TS section 4.4.1.2.a and 10 CFR 50, Appendix J, "Primary Reactor Leakage Testing for Water-Cooled Power Reactors."
The NRC staff has reviewed the proposed basis change regarding the operation of the PPS and has no objection to your proposed change.
Enclosed is a copy of the revised Basis page.
Sincerely, Brenda Mozafari, Project Manager Project Directorate II-1 Division of Reactor Projects -
I/II Office of Nuclear Reactor Regulation Docket No. 50-261
Enclosure:
Basis page 4.4-10 cc w/enclosure: See next page
Mr. C. S. Hinnant H. B. Robinson Steam Electric Carolina Power & Light Company Plant, Unit No. 2 cc:
Mr. R. E. Jones Mr. Dayne H. Brown, Director General Counsel - Legal Department Department of Environmental, Carolina Power & Light Company Health and Natural Resources Post Office Box 1551 Division of Radiation Protection Raleigh, North Carolina 27602 Post Office Box 27687 Raleigh, North Carolina 27611-7687 Karen E. Long Assistant Attorney General Mr. Robert P. Gruber State of North Carolina Executive Director Post Office Box 629 Public Staff - NCUC Raleigh, North Carolina 27602 Post Office Box 29520 Raleigh, North Carolina 27626-0520 U.S. Nuclear Regulatory Commission Resident Inspector's Office Mr. Max Batavia, Chief H. B. Robinson Steam Electric Plant South Carolina Department of Health 2112 Old Camden Road Bureau of Radiological Health Hartsville, South Carolina 29550 and Environmental Control 2600 Bull Street Regional Administrator, Region II Columbia, South Carolina 29201 U.S. Nuclear Regulatory Commission 101 Marietta St., N.W., Ste. 2900 Mr. J. Cowan Atlanta, Georgia 30323 Manager Nuclear Services and Environmental Mr. Dale E. Young Support Department Plant General Manager Carolina Power & Light Company Carolina Power & Light Company Post Office Box 1551 - Mail 0HS7 H. B. Robinson Steam Electric Plant Raleigh, North Carolina 27602 3581 West Entrance Road Hartsville, South Carolina 29550 Public Service Commission State of South Carolina Post Office Drawer 11649 Columbia, South Carolina 29211 Mr. R. M. Krich Manager - Regulatory Affairs Carolina Power & Light Company H. B. Robinson Steam Electric Plant, Unit No. 2 3581 West Entrance Road Hartsville, South Carolina 29550
Secondly, the penetration pressurization system is capable of continuously or periodically monitoring leakage from potential leak paths, such as.
penetrations, double gasketed seals. and spaces between certain containment isolation valves.
Total leakage from the system is measured by summing the recorded flows in each of the four penetration headers. The penetration pressurization system is a qualified system for continuous or intermittent pressurization of individual or groups of containment penetrations as allowed in 10 CFR 50. Appendix J. Items III.B.1.(b), III.B.3.(b). and III.C.1.
A flow sensing device is located in each of the headers supplying make-up air to the four pressurized zones. A leakage rate alarm is provided in each of the four indicating channels to alert the operator in the control room. The flow measurement accuracy is within +/-1%. A flow of 0.04% of the containment volume per day at 42 psig is approximately 0.58 ft'/minute (2.34 scfm).
The flowmeters are capable of indicating leakage well within these limits.
Containment isolation valves are designed to incorporate positive barriers to prevent or minimize leakage through the valves under design basis accident conditions. Several isolation valves are pressurized by the penetration pressurization system to prevent leakage. The remaining valves either receive Isolation Seal Water System water or are installed in systems that are part of a closed system within the containment or operate at system pressures greater than 42 psig in the post-accident condition. These design features provide positive means to prevent containment leakage through the containment isolation valves.
The limiting leakage rates from the recirculation heat removal system are judgment values based primarily on assuring that the components could operate without mechanical failure for a period on the order of 200 days after a design basis accident. The test pressure, 350 psig, achieved either by normal system operation or hydrostatically testing, gives an adequate margin over the highest pressure within the system after a design basis accident.
4.4-10 REVISED BY NRC LETTER DATED October 13, 1995