ML20128N588
| ML20128N588 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 02/11/1993 |
| From: | Dyer J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20128N590 | List: |
| References | |
| GL-91-08, GL-91-8, NUDOCS 9302230307 | |
| Download: ML20128N588 (24) | |
Text
. _ _ - _ _ _ _ _ _ - - _
/
"o UNITED STATES t
NUCLEAR REGULATORY COMMISSION g
j WASHING TON, D, C. 20bsS
\\....+/
COMMONWEALTB EDISON COMPANY DQMfT NO. 50-237 ORESDEN NUCLEAR POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.122 License No. DPR-19 1.
The Nuclear Regulatory Commission (the Commission) has found th t:
A.
The application for amendment by the Commonwealth Edison Company (the licensee) dated September 2, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as-amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations:
D.,
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-i cations as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-19 is hereby l
amended to read as follows:
- s8agggg;oggggg7
-P.
. (2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 122 are hereby incorporated in the license.
The licensee. hall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance, to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Qu162. der y
mes E. Dyer, Director Project Directorate 111-2 Division of Reactor Projects - lil/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: February 11, 1993 (I
1 I
l
4 ATTACHMENT TO LICENSE AMENDMENT NO. 122 FACILITY OPERATING tlCENSE NO. OPR-19 QQCKET NO. 50-237 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by the captioned amendment number and contain marginal lines indicating thefarea of change.
t REMOVE INSERT.
vii vii 1-0.3 1-0.3 3/4.7-6 3/4.7-6 3/4.7-9 3/4.7-9 3/4.7-?7 3/4.7-27 3/4.7-28 3/4.7-28 3/4.7-29 3/4.7-29 3/4.7-31 3/4.7 :
B 3/4.7-40 B 3/4.7-40~
B 3/4.7-46 B3/4.7-46_
i l
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- ~. -
l DRESDEN II DPR-19 Amendment No. 122 List of Tables
.P,,ag Table 3.1.1 Reactor Protection System (Scram) 3/4.1-5 Instrumentation Requirements Table 4.1.1 Scram Instrumentation Functional Tests 3/4.1-8 Table 4.1.2 Scram Instrumentation Calibration 3/4.1-10 Table 3.2.1 Instrumentation that Initiates Primary Containment Isolation Functions 3/4.2-8 Table 3.2.2 Instrumentation that Initiates or Controls the Core and Containment Cooling System 3/4.2-10 Table 3.2.3 Instrumentation that Initiates Rod Block 3/4.2-12 Table 3.2.4 Radioactive Liquid Effluent Monitoring Instrumentation 3/4.2-14 Table 3.2.5 Radioactive Gaseous Effluent Monitoring Instrumentation 3/4.2-15 Table 3.2.6 Post Accident Monitoring Instrumentation Requirements 3/4.2-17 Table 3.2.7 Instrumentation That Initiates Recirculation Pump Trip 3/4.2-18a Table 4.2.1 Minimum Test and Calibration Frequency for Core and Containment Cooling Systems Instrumentation, Rod Blocks, and Isolations 3/4.2-19 Table 4.2.2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements 3/4.2-22 Table 4.2.3 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 3/4.2-24 Table 4.2.4 Post Accident Monitoring Instrumentation Surveillance Requirements 3/4.2-26 Table 4.2.5 Minimum Test and Calibration Frequency for the Recirculation Pump Trip 3/4.2-27a Table 4.5.1 Surveillance of the HPCI Subsystem 3/4.5-7a Table 4.6.2 Neutron Flux and Sample Withdrawal B 3/4.6-26 Table 3.7.1 Deleted per requirements of Generic Letter 91-08 l
Table 4.8.1 Radioactive Gaseous Waste Sampling and Analysis Program 3/4.8-22
+
Table 4.8.2 Maximum Permissible Concentration of Dissolved or Entrained Noble Gases Released From the Site to Unrestricted Areas in Liquid Waste 3/4.8-24 Table 4.8.3 Radioactive Liquid Waste Sampling and Analysis Program 3/4.8-25 Table 4.8.4 Radiological Environmental Monitoring Program 3/4.8-27 Table 4.8.5 Reporting Levels for Radioactivity Concentrations in Environmental Samples 3/4.8-28 Table 4.8.6 Practical Lower Limits of Detection (LLD) for Standard Radiological Environmental Monitoring Program 3/4.8-29 vii
DRESDEN II DPR-19 Amendment No.122 1.0 Definitions (Continued)
R.
Primary Containment liiteority - Primary containment integrity means that the drywell and pressure suppression chamber are intact and all of the following conditions are satisfied:
1.
All manual containment isolation valves on lines connecting to the reactor coolant system or containment which are not required to be open during accident conditions are closed or I
comply with the requirements of Specification 3.7.D.
l 2.
At least one door in each airlock is closed and sealed.
3.
All automatic containment isolation valves are operable or deactivated in the isolated position or comply with the i
requirements of Specification 3.7,0.
4.
All blind flanges arid manways are closed.
5.
Protective Instrumentation Definitions 1.
Instrument Channel - An instrument channel alans an arrangement of a sensor and auxiliary equipms nt required to generate and transmit to a trip system a single trip signal re W d to the plant parameter monitertd by that instrur,ent chantial.
2.
Trip System - A trip system means an arrangement of instrument channel trip signals and auxiliary equipment required to initiate action to accomplish a protective trip function.
A trip system may require one or more instrument channel trip signals related to one or more plant parameters in order to initiate trip system action.
Initiation of protective action may require the tripping of a single trip system or the coincident tripping of two trip systems.
3.
Protective Action - An action initiated by the protection system when a limit is reached.
A protective action can ce at a channel or system level.
4.
Protective Function - A system protective action which results from the protective action of the channels monitor-ing a particular plant condition.
T.
Rated Neutron Flux - Rated neutron flux is the neutron flux tnat corresponds to a steady-state power level of 2527 thermal megawatts, U.
Rated Thermal Power - Rated thermal power means a steady-state power level of 2527 thermal megawatts.
I 1.0-3
4 ORESDEN II DPR-19 Amendment No. 122 3.7 LIMITING CONDITION FOR GPERATION 4.7 SURVEILLANCE REQUIREMENTS (Cont'd.)
(Cont'd.)
(1) An overall integrated leakage rate for Type A tests of:
(a) L less t8Inor equal to 75 percent of L'
a (b) L less tbinor equal to 75 percent of L.
g (2) (a) A combined leakage rate of less than or equal to 60 percent of L for allfestable penetrations and isola-tion valves subjectto Type B and C tests ex-cept for.
3/4.7-6
DRESDEN II DPR-19 Amendment No. 122 3.7 LIMITING CONDITION FOR OPERATION 4.7 SURVEILLANCE REQUIREMENTS TCont'd.)
(Cont'd.)
(1) Main steam line isolation valves which she.11 be tested at a pressure of 25 psig each operating cycie.
(2) Bo'ted deublemasketed s
seals w11ch shall be tested at a pressure of 48 psig whenever the seal is closed after being opened and each operating cycle.
(3) Air locks which shall be tested at 10 psig each operating cycle.
(4) Deleted f.
Continuous Leak Rate Monitor (1)Whenthe primary containment is inerted, the containment i
3/4.7-9
4 DRESDEN II
. DPR.
Amendeent No. 122 3,7 LIMITING CONDITION FOR OPERATION 4.7 SURVEILLANCE REQUIREMENTS-(Cont'd.)
TCont'd.)
S d.
The fuel cask or ir-radiated fuel is not being moved in the reactor building.
e 2.
Specification 3.7.C.1
^
- t..anot be met, restore Sccor.dary Containment Integt 4ty within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in Cold Shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and establish the condit.ans listed in Specification 3.7.C.1.a through d.
D.
Primary Conteinment Isolation Valves Isolation Valves 1.
During reactor power 1.
The primary containment operating isolation valves-co:Jitions, all surnillance shall be primary containment performed as follows:
isolation valvos and all instrument a.
At least-once per line flow check operating cycle-the valves shall be operable primary-operable except containment llola-as '-ecified in tion valtes.that 3.7.0.2.
are power operated and adtomatically initiated shall be tested for simulated automatic initiation and closure times.
3/4.7-27
~-
DRESDEN 17 DPR-19 Amendment No. 122 3.7 LIMITING CONDITION FOR OPERATION 4.7 SURVEILLANCE REQUIREMENTS (Corit' d. )
(Cont'd.)
b.
At least once per operating cycle the instrument line flow check valves shall be tested for proper operatio.
c.
At least once per quarter:
(1) All normally open power-operated isola-tion valves (except for the c"
[
power-operated isolation valves) shall
~
be fully closed and reopened.
(2) With the re tor power less-than 50% of rated, trip main steam isolation valves (one at a time) and verify closure-
- time, d.
At-least twice per week the main steamline power-operated isolation valves shall be exercised by partial closure and subsequent reopening.
2.
In the event any 2.
Whenever a primary contain-primary containment ment isolation valve is isolation valve inoperable, the position of becomes inoperable, at least one other valve reactor power in each line having an operation may continue inoperable valve shall be provided at least recorded daily, one valve in 3/4.7-28
s DRESDEN Il-DPR-19' Amendment No.122 3.7 LIMITING CONDITION FOR OPERATION 4.7 SURVEILLANCE ~REQUIREHENTS (Cont'd.)
(Cont'd.).
each line having an in-operable valve is in the inode corresponding to the isolated condition.
3.
If Specification 3.7.D.I 3.
The temperature of-the and 3.7.D 2 cannot be main steamline air _
met, an orderly shutdown pilot valves shall be shall be initiated and recorded daily, the. reactor shall be in the Cold Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> except for the Recirculation loop Sample valves and the Drywell Air Sampling System valves which can be reopened after isolation for sampling.
4.
T; e temperature of 4.
When it is determined -
the main steamline that the temperature of air pilot valves any main steamline air shall be less than pilot valve is greater 170 F except as than 170*F, the main specified in 3.7.0.5 steamline isolation below.
valves shall be demonstrated to be operable immediately and daily;thereafter.
The demonstration of
-operability shall_be according to Specification 4.7.D.1.d.
5.
From and after the cate that the temperature of any main steamline air pilot valve is found to be greater than 170'F.
reactor operation is permissible only during the' succeeding-seven cays unless the temperature of such valve is sooner reduced to less than_170*F, provided the main steamline isolation valves are operable.
3/4.7-29'
~
f.
~
DRESDEN II DPr. 19 Amendment'No. 122 3.7 LIMITING CONDITION FOR OPERATION BASES (Cont'd.)
standby gas. treatment subsystems significantly different from the design. flow will change the removal efficiency of the HEPA filters and charcoal adsorbers.. If the performance require-ments are met as specified, the calculated. doses would be less than the guidelines stated in 10 CFR 100 for the accidents analyzed.
D.
Primary Containment Isolation Valves - Double isolation valves are provided on lines penetrating the primary containment and open to the free space of the containment.
Closure of one of the valves in each line would be sufficient to maintain the integrity of the pressure suppression system.
Automatic initiation is required to minimize the a tential leakage paths from the containment in the event of a
.ss of ::oolant -
accident.
A controlled list of the primary containment isolation valves is located within the Dresden Administrative Technical Requirements.
4.7 SURVEILLANCE REQUIREMENT BASES A.
Primary Containment Because of the large volume and thermal capacity of the suppression pool, the volume and temperature normally. changes very slowly and monitoring these parameters daily is sufficient t 9stablish any temperature trends.
By= requiring the suppres. On pool temperature to be continually monitored and frequently logged during periods of significant heat-additior;, the temperature trends will-be closely followed so that apptcpriate action can be takers.
The requirement for an external visual examination following any event where potentially bigh loadings could occur provides assurance-that no significant damage was encountered.
Particular attention should be focused on structural discontinuities-in-the vicinity of the relief valve discharge since these are expected to be-the points of highest stress.
The interiors of the drywell and suppression chamber are painted tc prevent rusting.
The inspection of the paint' during each major refueling outage,'approximately once per year, assures the paint is intact.
Experience'with this type of paint at fossil fueled generating stations indicates-that the inspection interval is adequate.
B 3/4.7-40
1 o
~DRESDEN-II
- DPR-19 Amendment No.1122L 4.7. SURVEILLANCE'REQUIREMENTBASES(Cont'd.)l analysis should be performed as required for. operational use.
Replacement adsorbent should be qualified;according to the.
guidelines of Regulatory Guide 1.52,- Revision 1 (June 1976).D The charcoal adsorber efficiency test procedures will allow for the removal of one representativeLsample: cartridge and testing in accordance with the guidelines of Table 3 of-Regulatory Guide 1.52,- Revision 1 (June.1976). LThe samplei will be at least two inches in-diameter and a length-equal to.
the thickness of the bed. :If the iodine removal. efficiency-test results are unacceptable,.all adsorbent in the system will be replaced.
High efficiency particulate filters are-installed before and after the charcoal filters to prevent, clogging of the carbon adsorbers andito minimize potential?
release of particulates to the environment.
An efficiency of-99% is adequate to retain particulates that may be-released to the reactor building following-an accident.
This will be.
demonstrated by in place testing-with DOP as the testing.
medium.
Any HEPA filters found defective will be replaced with filters qualified p'ursuant to regulatory guide ^ position -
3 C.3.d of Regulatory Guide 1.52,. Revision 1 (June 1976).
Once.
~
per operating cycle demonstration of-HEPA filter pressure-
= drop, operability of inlet heaters at rated power, air.-
distribution to each HEPA filter, and automatic initiation:of each standby gas treatment system subsystem is necessary tn assure system performance capability..
D.
Primary Containment Isolation Valves Those large fipos comprising a portion of the-reactor cuolant system, whose failure could result 'ia uncovering the reactor:
core, are supplied with automatic isolation' valves.-(except'-
those fines needed for emergencyLeore cooling 1 system operation-or containment cooling). -The closure times are adequate to prevent-
- l loss of nore coolant from the circumferential rupture of any of-these lines outside the containment than from a steam line rupture.-
l Therefore, the isolation valve' closure times are-sufficient'to l-l prevent uncovering the core.
L B 3/4.7-46 r
f UNITED STATES e I'b ;k NUCLEAR REGULATORY COMMISSION I
O Q w})/.
WA SHING TON, D. C. 20555 I
3..v COMMONWEALTH EDIS0N COMPANY DOCKET NO. 50-249 DRESDEN NUCLEAR POWER STATION. UNil 3 AMENDMENT TO FACIllTY OPERATING LICENSE
- Amendment No.- 117 License No. DPR-25 1.
The Nuclear Regulatory Commission (the Commission) has fcund that:
A.
The application for amendment by the Commonwealth Edison Company (the licensee) dated September 2, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954,-as amended (the Act), and the Commission's rulos and regulations set.
forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application,.the provisions of the Act and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment wii' not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi--
cations as indicated in the attachment to this license amendment and paragraph 3.B. of Facility Operating License No. DPR-25 is hereby amended to read as follows:
4
.- ^
B.
Technical Specificat' ions The Technical Specifications contained-in Appendix A, as revised through Amendment No. 117,. are hereby incorporated in the license. The licensee shall operate the facility in at:ordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance, to-be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION t&Ms t, eu oames E. Dyer, Director Project Directorate III-2 Division of Roactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Speci fications Date of Issuance:
February 11, 1993 l
l s
i I
l l
a ATTACHMENT TO LICENSE AMENDMENTi NO. '117; FACILITY OPERATING LICENSE:NO. OPR-25 DOCKET'NO.'50-249 Revise the Appendix A Technical Specifications-by removing the pages identified below and inserting the attached pages. The revised pages:are identified by the captioned amendment number and contain marginas lines-indicating the area of change.
REMOVE INSERT vii vii-1-0.3 0;3-3/4.7-6 3/4 7-6 3/4.7-9 3/4.7-9 3/4.7-27 3/4.7 '
3/4.7-28 3/4.7-28 3/4.7-29 3/4.7 t-
-3/4.7-31 3/4.7-32 B 3/4.7-40 B 3/4.7-40 8 3/4.7-46 8 3/4.7 !
l-l-
l l..
L l
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9 m
m
DRESDEN III DPR-25 List of Tables Amendment No. 117 Table 3.1.1-ReactorProtectionSystem(Scram) 3/4.1-5 Instrumentation Requirements Table 4.1.1 Scram Instrumentation Functional Tests
-3/4.1-8 Table 4.1.2 Scram-Instrumentation Calibration 3/4.1 Table 3.2.1 Instrumentation that Initiates Primary Containment Isolation Functions 3/4.2-8 Table 3.2.2 Instrumentation that Initiates or Controls the Core and Containment Cooling System 3/4.2-10 Table 3.2.3 Instrumentation that Initiates Rod Block 3/4.2-12 Table 3.2.4 Radioactive Liquid Effluent Monitoring Instrumentation 3/4.2-14 Table 3.2.5 Radioactive Gaseous Effluent 3/4.2-15 Monitoring Instrumentation Table 3.2.6 Post Accident Monitoring Instrumentation Requirements 3/4.2-17 Table 3.2.7 Instrumentation That Initiates Recircula-tion Pump Trip 3/4.2-18a Table 4.2.1 Minimum Test and Calibration Frequency for Core and Containment Cooling Systems Instrumentation, Rod Blocks, and Isolations 3/4.2-19 Table 4.2.2 Radioactive Liguid Effluent Monitoring Instrumentation Surveillance Requirements 3/4.2-22 Table 4.2.3 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 3/4.2-24 Table 4.2.4 Post Accident Monitoring Instrumentation Surveillance Requirements 3/4.2-26 Table 4.2.5 Minimum Test and Calibration Frequency for Recirculation Pum) Trip 3/4.2-27a Table 4.5.1 Surveillance of HPCI Su> system 3/4.5-7a Table 4.6.2 Neutron Flux and Sample Withdrawal B 3/4.6-30 Table 3.7.1 Deleted per the requirements of Generic Letter 91-08 l
Table 4.8.1 Radioactive Gaseous Waste Sampling and Analysis Program 3/4.8-22 Table 4.8.2 Maximum Permissible Concentration of Dissolved or Entrained Noble Gases Released from the Site to Unrestricted Areas in Liquid Waste 3/4.8-24 Table 4.8.3 Radioactive Liquid Waste Sampling and Analysis Program 3/4.8 Table 4.8.4 Radioactive Environmental Monitoring Progran 3/4.8-27 Table 4.8.5 Reporting levels for Radioactivity Concentrations in Environmental Samples 3/4.8-28 Table 4.8.6 Practical Lower Limits of Detection (LLD) for-Standard Radiological Environmental Monitoring Program 3/4.8-29 Table 4.11-1 Deleted.
Table 3.12-1 Deleted.
vii
DRESDEN III DPR Amendment No. 117 1.0 DEFINITIONS (Cont'd.)
R.
Primary Containment Integrity - Primary containment integrity means that lhe drywell and pressure suppression chamber are intact and all y
of the following conditions are satisfied:
1.
All manual containment isolation valves on lines connecting to the reactor coolant system or containment which are not required to be open during accident conditions are closed or comply with the requirements of Specification 3.7.D.
- 2..At least one door in each airlock is closed and sealed.
3.
All automatic containment isolation valves are operable or deactivated in the isolated position or comply with the requirements of Specification 3.7.D.
4.
All blind flanges and manways are closed.
5.
Protective Instrumentation Definitions 1.
Instrument Channel - An instrument channel means an arrangement of a sensor and auxiliary equipment required to generate and transmit to a trip system a single trip signal related to the plant parameter monitored by that instrument channel.
2.
Trip System - A trip system means an arrangement of instrument channel trip signals ano auxiliary equipment required to initiate action to accomplish a protective trip function.
A trip system may require one or more instrument channel trip tignah related to one or more plant parameters in order to ini' late trip system action.
Initiation of protective action may require the tripping of a single trip _ system or the coincident tripping of two trip systems.
3.
Protective Action - An action initiated by the protection system when a limit is reached.
A protective action can be at a channel or system level.
4.
Protective Function - A system protective action which results from the protective action of the channels monitoring a particular plant condition.
T.
Rated Neutron Flux - Rated neutron flux is the neutron flux that-corresponds to a steady-state power level of 2527 thermtl megawatts.
U.
Rated Thermal Power - Rated thermal power means a steady-state power level of 2527 thermal megawatts.
l 1.0-3
DRESDEN III
-DPR-25
' Amendment No.117-
- ]
-- 3. 7 LIMITING CONDITION FOR-OPERATION-4.7.--SURVEILLANCE REQUIREMENTS TCont'd.)
(Cont'd.)
~
~
(1) An overall integrated leakage-rate for Type A tests of:
(a) L less tfiInor equal to 75 percent of
-eg.
1 (b) L,less tflanor equal to 75 percent of L.
t (2) (a) A combined leakage rate of less than or equal to 60 percent of L for all festable penetrations and isola-tion valves subject to Type B and C tests except for main stese isola-tion valves.
3/4.7-6 c
DRESDEN III
'DPR.
Amendment No.117 3.7. LIMITING CONDITION FOR OPERATION-4.7. SURVEILLANCE REQUIREMENTS (Cont'd.)
TCont'd.)
(2) Bolted double-gasketed seals; which shall be
. tested at a.
pressure of 48 psig--
whenever the seal is closed after being opened and each operating cycle.
(3) Air locks which shall be testedi at 10 psig.each operating cycle.
(4) Deleted; f.
Continaous Loak Rate Monitor-
.(1) When the pri;1ary con -
tainment is inerted,-.the containment shall be continuously J
~ monitorednfor grost loakage by. review off the inerting:-
system make-up regt,irements.
b
'3/4.7-9 o
e
_n 1
IDRESDENIII-
-DPR ~
Amendment No. :117 3.7 LIMITING CONDITION FOR OPERATION 4.7. SURVEILLANCE REQUIREMENTS (Cont'd.)
[ Cont'd.)
d.
The fuel cask or irradiated fuel is not being moved in the reactor building.
2.
If Specific.ation 3.7.C.1 cannot be met, restore Secondary Containment Integrity within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in' Cold Shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and establish the conditions listed in Specificatien y.
3.7.C.I.a through d.
D.
Primary Containment D. - Prinary Containment -
Isolation Valves Isolation Valves 1.
Ouring reactor power
_2. : The primary containinent operating isolation valves conditions, alI primary surveillance chall bai containment isolation performed as follows:.
valves and all-a.
At least-once per-instrument line flow
. operating cycle _the check valves shall operable _ primary l
be operable except
. containment isola-as specified in tion valves-that '
3.7,0.2.
-are power operated s
and automatically.
s initiated shall be tested for simulated
-automatic' initiation' and closure times.
b.
.At least once per operating. cycle the
-instrument line flow check valves shall'be tested for
< ^
proper operation.
4 3/4.7-27
I CRESDENli!
~DPR-s5'
' Amendment No.11L 3.7 LIMITING CONDITION FOR OPERATION
-4.7 SURVEILLANCE REQUIREMENTS
[ Cont' d. )
(Cont'd.)-
'c,
'At least once per quarter:
(1) All normally-open power -
operated isola-tion valves (except for the-main steam line powe r-operated isolation valves) shall be fully closed-and reopened.
(2) With'che reactor power less than 50% of rated,.
trip main steam -
isolation valves (one at a time) and verify c'iosure - time.
a.
At-least twice per week tne main steam-
- line power-cperated
' solation valves i
shall be exercised by partial closure and. subsequent-reopening.
4 2.
In the event any 2.
Whenever a primary contain-primary containment ment isolation valve is isolation valve becomes inoperable, the position of.
inoperable, reactor at least one other. valve power operation may in each line having an continue provided at inoperable valve shall be-least one valve in recorded daily.
each-line having an inopcrable valve. is in the mode corresponding to the isolated candition.
3/4.7-28
~
S-DRESDEN!!!!i.
=
Amendment NoL.DPR-2 117:
3.7 = LIMITING CONDITION FOR OPERATION-4.7f SVRVEILLANCE REQUIREMENTS:
(Cont'd.)-
-(Cont'd.)
a-3.
If Specification 3.7.D.1 3.-ITh'etemperatureofLthe-and:3.7.D.2 cannot'be met.-
-main ~ steaaline _ air:
an orderly shutdown shall pilot.valvesisha11 be?
be initiated and the reactor recorded daily.
M shall be'in the Cold '
Shutdown: condition within
~
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> except for the Recirculation Loop. Sample valves and the Drywell Air Sampling System valves 1 which can be reopened after.
isolation for sampling.--
4.
The temperature of 4.
When it'is determined the main steamline.
that the: temperature ofc air pilot' valves any main steamline airi shall be'1ess than pilot = valve _is greater 170*F except as than-170*F, the main specified in 3.7.0.5 ster.mline isolation below.
valves shall be' demonstrated to be-
_ operable _.immediately:
.and daily _thereafter.-
-The demonstration of operability-shall be according1to Spect-fication 4.7.D.I.d.'
5.
From and after the date that the temperature of any main steamline air:
pilot valve is found.to E
_be greater;than 170*F,_
reactor-operation is permissible only during.
l the succeeding seven l=
days unless.- the -
u
. temperature of;such valve is sooner reduced L
to less than-170'F, provided_the. main steamline isolation valves are_ operable.-
v d-3/4.7-29 l'
~
DRESDEN III DPR-25 Amendment No. 317 3.7 LIMITING CONDITION-FOR OPERATION BASES (Cont'd.)-
results indicate a radioactive methyl iodide removal-efficiency for expected accident conditions.
Operation of the standby gas treatment subsystems significantly different-from the design flow will change the removal efficiency of_
the HEPA filters and charcoal adsorbers.- If the performance requirements are met as specified, the calculated deses would be less than the guidelines stated in 10 CFR 100 for the accidents analyzed.
D.
Primary Containment Isolation Valves -' Double isolation valves-are providad on lines peiietrating the primary containment and open to the free space of the containment.. Closure of one of-the valves in each line would be sufficient to maintain the integrity of the pressure suppression syttem.
Automatic ini-tiation is required to minimize the potential leakage paths from the containment in the event of a loss of coolant accident.
A controlled list of the primery containment isolation valves is located within tne Dresden Administrative Technical Requirements.
4.7 SURVEILLANCE REQUIREMENT BASES A.
Primary Containment Because of the large volume and thermal capacity of the suppression pool, the volume and temperature normally changes very slowly and monitoring these parameters daily is suffi-cient to establish any temperature trends.
By requiring the suppression pool temperature to be continually monitored and frequently logged during periods of significant heat addition,-
the temperature trends will be closely followed so that appro-priate action can be taken.
The requirement for an external visual examination following any event where potentially high i
l loadings could occur provides assurance that no significant damage was encountered.
Particular attention;should be focused on structural discontinuities in the vicinity of the i
relief valve discharge since these are expected to be the points of highest stress.
The interiors of the drywell and suppression chamber are l
l painted to prevent rusting.
The inspection of the paint during each major refueling outage, approximately once per year, assures the paint is intact.
Experience with this type of paint at fossil fueled generating stations indicates that l
the inspection interval is adequate.
L l
B 3/4.7-40 t-
e
.t DRESDEN'III DPR-25 Amendment No. 117 4.7 SURVEILLANCE REQUIREMENT BASES (Cont'd.)
analysis should be performed as required for operational use.
Replacement adsorbent should be qualified according to the guidelines of Regulatory Guide 1.52, Revision 1 (June 1976).
The charcoal adsorber efficiency test procecures will allow for the removal of one representative shmple cartridge and testing in accordance with the guidelines of Table 3 of Regu-latory Guide 1.52, Revision 1 (June 1976).
The sample will-be at least two inches in diameter and a length equal to the thickness of the bed.
If the iodine removal efficiency test results are unacceptable, all adsorbent in the system wi'l be replaced.
High efficiency particulate filters are installed before and after the charcoal filters to prevent clogging of the carbon adsorbers and to minimize potential release of particulates to the environment.
An efficiency of 99% is adequate to retain particulates that may be released to the reactor building following an accident.
This will be demon-strated by in place testing with DOP as the testing medium.
Any HEPA filters found defective will be replaced with filters qualified pursuant to regulatory guide position C.3.d of Regu-latory Guide 1.52, Revision 3 (June 1976).
Once per operating cycle demonstration of HEPA filter pressure drop, operability of inlet heaters at rated power, air distribution to :ach HEPA filter, and automatic initiation of each standby gas treatment.
system subsyscem is necessery to assure system performance capability.
D.
Primary Containment Isolation Valves Those large pipes comprising a portion of the reactor coolant system, whose failure could result in uncovering the reactor core, are supplied with automatic isolation valves (except those lines needed for emergency core cooling system operation or containment cooling).
The closure times are adequate to prevent {
loss of more coolant from the circumferential_ rupture of any of these lines outside the containment than from a steam.line rupture.
Therefore, the isolation valve closure tiiacs are sufficient to l
prevent uncovering the core.
B 3/4.7-46 i
A