ML20058M778
| ML20058M778 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 10/07/1993 |
| From: | NORTHEAST UTILITIES |
| To: | |
| Shared Package | |
| ML20058M764 | List: |
| References | |
| NUDOCS 9312210105 | |
| Download: ML20058M778 (3) | |
Text
'
A APPENDIX A U
CATEGORY I SYSTEMS, STRUCTURES, AND COMPONENTS The following systems, structures and components of a nuclear power plant, including their foundations and supports, are designated as Category I.
The pertinent quality assurance requirements of Appendix B to 10 CFR Part 50, should be applied, as a minimum, to all quality activities affecting the safety function of these systems, structures, and components as listed below and to other items and services specifically identified by NU in each FSAR addressing Section 3.2.1 of NRC Regulatory Guide 1.70.
t (a)
The reactor coolant pressure boundary.
(b)
The reactor core and reactor vessel internals.
l (c)
Systems or portions of systems that are required for (1) emergency core cooling; (2) post-accident containment heat removal or; (3) post-accident containment atmosphere cleanup (e.g., hydrogen removal system).
(d)
Systems or portions of systems that are required for (1) reactor shutdown; (2) residual heat removal or; (3) cooling the spent fuel storage pool.
(e)
Those portions of the steam systems of boiling water reactors extending from the outermost containment isolation up to but not including the turbine stop valve, and connected piping of 2-1/2 inches or larger nominal pipe size up to and including the first valve that is either normally closed or capable of automatic closure during all modes of normal reactor operation.
(f)
Those portions of the steam and feedwater systems of pressurized water reactors extending from and including the secondary side of steam generators up to and including the outermost containment isolation valves, and connected piping of 2-1/2 inches or larger nominal pipe size up to and including the first valve (including a safety or relief valve) that is either normally closed or capable of automatic closure during all modes of normal reactor operation.
(g)
Cooling water, component cooling and auxiliary feedwater systems or portions of these systems including the intake structures, that are required for:
(1) emergency core cooling; (2) post-accident containment heat removal; (3) post-accident containment atmosphere cleanup; (4) residual heat removal from the reactor or; (5) cooling the spent fuel storage pool.
QAP - Appendix A Rev.: 16 Date: October 7,1993 9312210105 931206 3
Page 1 of 3 PDR ADOCK 05000213 p
PDR i
j i
4 (h)
Cooling water and seal water systems or portions of these systems that are j
required for functioning of safety related reactor coolant system components such as PWR reactor coolant pump seals.
1 j
i (i)
Systems or portions of systems that are required to supply fuel for emergency j
j.
equipment.
f (j)
All electrical and mechanical devices and circuitry between the process and the j
actuated devices involved in generating or responding to signals that provide protective functions of safeguard systems.
(k)
Systems or portions of systems that are required for (1) monitoring of systems-safety-related and; (2) actuation of systems safety-related.
" Required for monitoring," i.e. Those parameters that provide information that
-is essential to permit the control room operator to take specific manually controlled actions for the direct accomplishment of the specified safety function.
(1)
The spent fuel storage pool structure, including the fuel racks.
(m)
The reactivity control system (e.g., control rods, control rod drives, and boron injection system).
l O
(n)
The control room, including its associated equipment and all equipment needed 1
to maintain the control room with safe habitability limits for personnel and safe environmental limits for vital equipment.
(o)
Primary and secondary reactor containment.
(p)
Systems other than radioactive waste management systems not covered by items (a) through (o) above which contain or may contain radioactive materials and whose postulated failure would result in conservatively calculated potential offsite '
doses (using meteorology as prescribed by Regulatory Guides 1.3 and 1.4) which are more than 0.5 rem to the whole body or its equivalent to any part of the body.
1 (q)
The Class IE electric systems, including the auxiliary systems for the onsite electric power supplies, that provide the emergency electric power needed 'for functioning of plant features included in items (a) through (p) above.
(r)
Those portions of systems, structures or components whose continued function is not required but whose failure could reduce the functioning of any plant-feature included in items (a) through (q) above to an unacceptable safety level or O
Q'AP - Appendix A Rev.: 16 J
Date: October 7,' 1993 Page 2 of 3 j
1
/
., _. ~, _,.
. ~.,.
......J
~
O
could result in incapacitating injury to occupants of the control room should be designed and constructed so that the SSE would not cause such failures.
(s)
Items and services associated with Radioactive Material Transport Packages as described in 10CFR71.
CONSUMABL ES.
The following specific consurnables when utilized in safety related systems shall be included in those portions of the NUQAP, as applicable.
1.
Emergency generator diesel fuels 2.
Hydraulic snubber fluids 3.
Reagents l
l l
4.
Resins 5.
Boric Acid 6.
Lubricants 7.
Gas Turbine Fuel l
i l
QAP - Appendix A Rev.: 16 l
Date: October 7,1993 Page 3 of 3