ML20028D438
| ML20028D438 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 12/30/1982 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20028D433 | List: |
| References | |
| NUDOCS 8301190119 | |
| Download: ML20028D438 (12) | |
Text
o *< coy n
![, 3 s, ( 3 jo UNITED STATES, g
g NUCLEAR REGULATORY COMMISSION
{.g
/-
WASHING TON, D. C. 20555 h
o., w ' v j' g
SAFETY. EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION APPENDIX R TO 10 CFR PART 50r ITEMS III.G.3 AND III.L QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 1.0 I N T R O D U C T I O'N On February 17, 1981, the fire protection rule for nuclea.r power plants,10 CFR 50.48 and Appendix R to 10 CFR Part 50, became effective.
This rule ' required a L L Licensees of plants Licensed prior to January 1, 1979 to submit
~by March 19, 1981: (1) plans and schedules for meeting the applicable requirements of Appendix R, (2) a design description of any modifications proposed to provide alternative safe shutdown capability pursuant to Paragraph III.G.3 of Appendix R, and (3) exemption requests for which the toL Ling provision of Section
~
50.48Cc)(6) was to be invoked.
Section III.G of Appendix R is a retrofit item to all pre-1979 plants l
rega rdles s of previous safety evaluation positions and r~esolutions.
The criteria contained in Section III.L of Appendix R-l l
are used for those cases where Licensees a re incorpo-l l
rating alternate or dedicated s,hutdown capability.
The staff's previous fire protection Safety Evaluation (SE) dated July 27,1979r identified no open items concerning the post fire safe shutdown capabilityr although the SE indicated that 8301190119 821230 PDR ADOCK 05000254 F
pgp
2 further analysis was being performed by the Licensee.
- Further, the SE identified no specific plant areas requiring alternate safe shutdown capability.
By submittats dated July 31, 1978, october 1, 1979, January 23, 1980, February '29, 1980, June 6, 1980, February 20, 1981, May 19, 1981, August 31, 1981, January 29,1982, Ma rch 10,1982, May 18,1982, July 1982, July 1,1982, and october 18,1982, t he Licensee described proposed modifications to the Quad Cities plants, Units 1 and 2, to meet the requirements of Appendix R to 10 CFR Part 50, Items III.G.3 and II,I.L.
The Licensee also responded to a staff request for i
additional information transmitted to the Licensee by Letter dated February 20, 1981.
Additional inf orma-tion and clarification was obtained through telephone conferences of, September 17, 1982 and September 22, 1982.
Th'e majority of the information on the safe shutdown capability is provided in the July 1982
" Fi re Protection Associated Circuits Analysis and Modifications Report."
l r
1 4
. Q The Licensee has provided a safe shutdown analysis for fire events and has demonstrated that adequate
~
systems exist and/or alternative safe shutdown cap-ability is available.
Our evaluation of this fotLovs.
2.0 POST-FIRE SAFE SHUTDOWN CAPABILITY 2.1 S 'y s t e m s Recuired for Safe Shutdown Shutdown of the r'eactor and reactivity control is pro-yided by the cont rol rods.
Primary coolant inventor 9 is maintained by either the reactor core isolation cooling system (RCIC) or a new safe shutdown makeup i
_o.,
pump.
Reactor coolant pres sure cont ro'L' is ma.ntained
'b y the primary relief valves.
Decay heat remov L and suppression pool cooling is provided by the residual heat removal (RHR) system and the RHR service water system.
The diesel generators are cooled by the dies ~eL generator cooling water system.
2.2 Areas Where Alternate Safe Shutdown Cacabitity is Reauired The Licensee examined the need for alternate saf e shut-l down capability of both units of the, plant for a fire in any fire, area (51 areas total).
For those areas where a fire results in loss of the RCIC system (24 areas) the Licensee has proposed to provide a
new safe shutdown eO l
- t
(
makeup pump as an alternate.
The safe shutdown makeup pump and RCIC system are.both required for fires in certain areas which necessitate simultaneous shutdown of both Units (3 areas - cable room, control room, and electric equipment room).
The Licensee has stated that installation of the new safe shutdown makeup pump and associated equipment wilL begin af ter NRC approval of the concept, i
l 4
2.3 Section III.G.2 of Accendix R The Licensee also indicated that alL other areas of the plant (24 areas) not required to have an alternate safe l
shutdown system wiLL comply with t'he requirements of l
Section III.G.2 of Appendix R, unless an exemption l
l request has been approved by the staff.
2.4 Alternet, safe shutdown svst em '
i l
The alternate safe shutdown system required for those areas not meeting Section III.G.2 or included in the l
l l
l i
l 1
5-O O
exemption requests consists of a new safe shutdown makeup pump and its assocated support systems and instrumentation.
The safe shutdown mak'eup pump is equivalent in capacity to the existing RCIC pump and serves as a subsitute for that pump should the RCIC system be unavailable due to a fire.
The new makeup pump l
is manua'LLy started at i ts switchgear and can be manually Loaded on to either the Unit 1 or 2 diesel generator in order to provide flow to either unit as necessary.
The pump is independent of alL areas containing equi -
ment associated with the RCIC system.
i Because the. makeup pump provides a comparable :afe e
shutdown function to that of the RCIC pump, the licensee will propose technical specifications equivalent to those for the RCIC pump in order to assure maximum availability for the makeup
~
pump.
3.0 EVALUATION 3.1 Performance Goals The alternate shutdown system described in Section 2.4 in. conjunction with existing plant systems wilL enable the achievement of th'e performance goals outlined in Section III.L of Appendix R as folLows:
4 3.1.1 R e,a c t i v i t y control Saf e shutdown of the reactor is performed by manual i
\\
scram of the control rods from the ' control room.
1 The control rods also provide subsequent reactivity control during cooldown.
i l
l 3.1.2 Reactor Coolant Inventory Reactor coolant makeup is provided by either the RCIC or new safe shutdown makeup pump if RCIC is unavailable.
The RCIC and shutdown makeup pump i
initially take suction from the contaminated con-densate storage tank.
Additional supply for the RCIC pump is provided by the suppression pool and-for the makeup pump by the service water system.
Control of these pumps is availabLe at Local stations.
Manual valve operations are required '
fotLowing fires in certain plant areas which may affect automatic RCIC operation.
3.1.3 Reactor Coolant Pressure Control Reactor coolant pressure control 'is provided by the relief valves with backup pressure control anb overpressure protection provided by the " target rock" and safety valves.
e
?
3.1.4 Reactor Decay Heat Removat Decay heat removal in hot' shutdown 1,s accomplished through the use of the relief valves discharging to the suppression pool, and flow from the RCIC and/or shutdown makeup pump.
For cooldown (suppression pool cooling) and cold shutdown, decay heat removat is provided by the resi' dual hea.t removal (RHR) system and the RHR service water system.
Utiliza-tion of RHR requires local manual operations for fires in certain plant areas that may affect normat' RHR operation.
(%
3.1.5 Process Monitorina Direct indication of process variables i
including reactor coolant Level, reactor coolant pres'sure, i
reactor coolant tenperature, suppression pool level and condensate storage tank Levet is pr'o-vided at Local panels and indicators.
Diagnostic monitoring available includes RHR service water pressure, RHR system pressure and'. flow, RCIC pressure and flow, and shutdown makeup pump pressure and flow.
l e
3.1.6 Subport Functions The diesel generators, diesel generator. cooling water system, RHR service water syst'em and essential ventilation systems are available to provide necessary support function's for the alter-nate shutdown system.
Control and monitoring capability for these support systems is also pro-vided at Local Locations.
l 3.2 ZJ-Hour Recuirement 1
The Licensee has indicated that the capability l
l exists to achieve cold shutdown within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> l
l after a fire event assuming no offsite power is u
avai la b Le.
3.' 3 Repairs The Licensee has indicated that no repairs are l
planned or are necessary in order to comply with i
the Appendix R post-fire safe shutdown requ.irements.
1 1
3.4 Associated Circuits and Isolation The Licensee conducted a review of the present electrical systems to determine the plant's l
capability to meet the associated circuit criteria 1
s e
~
as stated in Appendix R relating to safe shutdown and concluded that the existing electrical installation with some additional equipment modifications would satisfy these criteria.
Modifications are necessary to the circuitry for the three diesel generators, Unit 1 RCIC system and Units 1 and 2 RHR system in order to assure their operability in case of fire as addressed in subsequent paragraphs.
The Licensee has addressed associated circuits of concern as discussed below.
3.4.1 Common Power Source e
The Licensee stated that alL instrumentation and power circuits are protected or wilL be provided with coordinated protection by either circuit breakers or fuses.
3.4.2 common Enclosure As in the common power source case, the Licensee stated that associated circuits that share a common enclosure with those required f or safe shut-
, down are provided with circuit breakers and/or fuses.
't 3.4.3 Sourious Sionats
'The Licensee stated that fires in some fire zones can cause spurious signals which cou'Ld impair operation of the diesel generators.
Therefore, an isolated Local control station wiLL be provided to
~
assure proper diesel generator operation.
Similar isolated Local control will be provided for the RCIC and RHR' system components to assure their function and provide Local control.
High-Low pressure interface motor operated valves and motor operated vatves which are not needed for safe shut-down wi LL be deenergized in ordee,to prevent their spurious operation.
3.5 Safe Shutdown Procedures and Manpower The Licensee wilL revise existing safe shutdown
=
procedures to incorporate the above described alternate shutdoen method.
The Licensee further states that the revisions witL be made to assure that the necessary shutdown fu'nctions can be per-formed at a t L times by manpower available.
'?
Because a number of manual actions are required to assure safe shutdown for fires in major areas of s
e 0
e
i
- 11 o
the plant (i. e., cable room, electric equipment room and control room), we request that the Office
~
of Inspection and Enforcement fire protection l
review team conduct a walk-through of the required i
procedure and verify that the necessary actions can be taken within the specified time for as'suring safe shutdown.
1
\\
S S
e 9
O 6
m -
n.
4.0 CONCLUSION
We have reviewed the licensee's proposed alternate shutdown capability for Quad Cities in accordance with Appendix R criteria.
Based on that review, we conclude that the performance goals for accomplishing safe shutdown in the event of a fi re, i.e.,
reactivity co,ntrol, inventory control, decay heat removal, pressure control, process monitoring and support functions are met by the proposed alternate.
Therefore, we conclude that the requirements of Appendix R, Sections III.G.3 and II,I.L are satisfied.
However, once the alternate system is implemented,
(
the licensee will propose technical spacifications for the l
new safe shutdown makeuo oumo comoarable to those'currantly
[
existing for the RCIC oumo.
Dated: DEC 3 01982 Principal Contributor:
J. Hermiel 1
O t
I
-l
+ - -.
^