Proposed Tech Specs Deleting References to Plant Suppression Pool Water Volume from TS & Supporting Planned Mods to ECCS Suction Strainers in Upcoming Refueling OutageML20210P347 |
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Hope Creek  |
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Issue date: |
08/20/1997 |
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Public Service Enterprise Group |
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Shared Package |
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ML20210P339 |
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References |
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NUDOCS 9708270065 |
Download: ML20210P347 (4) |
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Category:TECHNICAL SPECIFICATIONS
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Qualifications of Operations Manager ML18101B3831996-05-22022 May 1996 Proposed Tech Specs,Requesting Approval of Changes to QA Program 1999-09-30
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217E0451999-09-30030 September 1999 Proposed Tech Specs Supporting Use of ABB-CE Fuel & Reload Analyses Beginning with Upcoming Cycle 10 ML20216E6201999-09-10010 September 1999 Revised Event Classification Guide,Including Rev 14 to Table of Contents & Rev 10 to Attachments 6,7 & 9 ML20211F9511999-08-26026 August 1999 Proposed Tech Specs Pages,Raising Condensate Storage Tank (CST) Low Level Setpoints & Corresponding Allowable Values Associated with Transfer of HPCI & RCIC Pump Suctions from CST to Suppression Pool ML20196E6541999-06-21021 June 1999 Proposed Tech Specs Pages for HCGS License Change Requests H99-02 & H99-05,dtd 990329 & 0524,respectively ML18107A3601999-06-0404 June 1999 Non-proprietary Tech Specs Pages Re Transfer of PSEG Ownership Interests & Licensed Operating Authorities to New, Affiliated Nuclear Generating Company,Pseg Nuclear LLC ML20195B5531999-05-24024 May 1999 Proposed Tech Specs Correcting Typos & Editorial Errors. 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[Table view] |
Text
. _ _ _ _ _ _ _ _ _.. _ _ _. _ _ _. _. _ _ _. _ _. _. _ _.
J Document Control Desk LR-H97505 l
' Attachinent 3 HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 l
DOCKET NO 50-354 SUPPRESSION POOL VOLUME REFERENCE DELETIONS i
TECHNICAL SPECIFICATION PAGES WITH PROPOSED CHANGES i
The following Technical Specifications for Facility Operating License No. NPF-57 are af fected by this change request:
Technical Specification Page l
3.5.3:
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EML'RGENCY CORE COOLING SYSTEMS 3/4.5.3 SUPPRESSION CHAMBER LIMITING CONDITION FOR OPERATION 3.5.3 The suppression chamber shalt be OPERABLE:
In OPERATIONAL CONDITION 1, 2 and 3 with e-eentefned-wate m olum e d a.
4t-.least-118,000 2
ft, q uivalentde Tn indicated 1 1o 65" qb k fy6 y.
b.
In OPERATIONAL CONDITION 4 and 5d with a-containfB 1
G1Taft#--
-57,390-f t', Heiveie'nt-to'an indicated level of 5.0" except that 4
the suppression chamber level may be e s than t e li t or may be drained provided that:
gs c e g
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)
1.
No operations are performed that have a potential for draining the reactor vessel, 2.
The reactor mode switch is locked in the Shutdown or Refuel
- position, 3.
The condensate storage tank contains at least 135,000 available' gallons of water, and 4.
The core spray system is OPERABLE per Specification 3.5.2 with an OPERABLE flow path capable of taking suction from the condensate storage tank and transferring the water through the spray sparger to the reactor vessel.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, 3, 4 and 5*.
ACTION:
In OPERATIONAL CONDITION 1, 2 or 3 with the suppression chamber water a.
level less than the above limit, restore the water level to within the limit within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT SNUTDOWN 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 />.
b.
In OPERATIONAL CONDITION 4 or 5* with the suppression chamber water level less than the above limit or drained and the above required conditions not satisfied, suspend CORE ALTERATIONS and all operations that have a potential for draining the reactor vessel and lock the reactor mode switch in the Shutdown position.
Establish SECONDARY CONTAINNENT INTEGRITY within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
- The suppression chamber is not required to be OPERABLE provided that the reactor vessel head is removed, the cavity is flooded or being flooded from the suppression pool,'the spent fuel pool gates are removed when the cavity is flooded, and the water level is maintained within the limits of Specification 3.9.8 and 3.9.9.
HOPE CREEK 3/4 5-8
s.
CONTAINMENT $YSTEMS 3/4.6.2 DEPRES$URI2ATION SYST[M$
$UPPRE$$10N CNAM8[R (IMITINGCONDITIONNROPERaf!0N 3.6.2.1 The suppression chamber shall be OP[RA8L[ with:
n.
The pool water:
WA 2
1.
wn.400-ft,nr222,cos d, elveientEd indicat g vel between 74.5" and 74.5" and a Maximum everale temperature of 95'F during OPERATIONAL 2.
l CON 0! TION 1 er 2, except that the maximum everage temperature may be permitted to increase to:
l a) 105'F during testing which adds heat to the suppression chamber.
b) 110'F with THERMAL POWER less than er equal to IX of 1
RATED THERMAL POWER.
l 3.
Maximum everage temperature of 95'F during OPERATIONAL l
C0H0! TION 3, except that the maximum everage temperature may be pemitted to increase to 120*F with the ea' n steam line isolation valves closed following a scras, b.
A total leakage between the suppression chamber and drywell of less than the equivalent leakage through a 1-inch dianster orifice at a difforential pressure ef 0.80 psig.
APPLICA51LITY: OPERATIONAL COW ITIONS 1, 2 and 3.
ACTION:
With the suppression chamber water level outside the above limits.
a.
restore the water level to within the limits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> er be in at least NOT $NUTDOWN within the next 12 hoves and in COLD ENUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
With the suppression chamber everage water temperature greater than 95'F and THENEL POWER gredter than 35 of RATED THERMAL POWER, Mstore the average temperature te less than er equal to 95'F within 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> or be in at least HDT 5NUTDOWN 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
$NUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, eacept, as pemitted above:
1.
With the suppression chamber average water temperature greater than 106'F during testing which adds heat to the suppmssion chamber, step al testing which adds heat to the suppression chamber and restore the average temperature te less than gl'F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at loest NOT SNUfDOWN within th next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUfDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.
With the s@pression chamber everage water temperature greater snan 110*F, place the reactor made switch in the shutdown posi-tien and operate at least one residual heat removal leap in the suppreshien pool coe. ling mode.
MDPE CRitK 3/4 6 12 e
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. -x a.
5.0 DESIGN FEATURES
$.1
$1TE EXCLUSION AREA AND MAP DEFINING UNRESTRICTED AREAS AND $1TE BOUNDAR 1RDTERTIvE GA5E005 AND LIQUID EFFLUENTS 5.1.1 The exclusion area shall be as shown in Figure 5.1.1-1.
Information regarding radioactive gaseous and liquid effluents which will allow identifica-tion of st.ructures and release points as well as definition of UNRESTRICTED AREAS within the SITE BOUNDARY that are accessible to HEM 8EPS OF THE PUBLIC, shall be t.s shown in Figure 5.1.1-1.
i l
LOW POPULATION ZONE 5.1.2 The low population zone shall be as shown in Fi The circle with the five mile radius is the low population zone. gure 5.1.2 1.
5.2 CONTAINMENT CONFIGURATION
- 5. 2.1 The primary containment is a steel structure composed of a spherical lower portion, a cylindrical miodle portion, and a hemispherical top head which form a drywell.
The drywell is attached to the suppression chamber through a series of downcomer vents.
The suppression chamber is a steel pressure vessel in the shape of a torus.
The drywell has a nominal free air volume of 169,000 cubic feet.
The suppression chamber has an air volupf._13J.,000'Ncubic feet and a water region ef-H6,^E;%ub b feetr e N
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DESIGN TEMPERATUR N K 55UR &
-v s>, p, 5.2.2 The primary containment is designed and shall be a.
Maximum internal pressure 62 psig, b.
Maximum internal temperature:
drywell 340'F.
suppression pool 310'F.
c.
Maximum external differential pressare 3 psid.
SECONDARY CONTAINMENT 5.2.3 The secondary containment consists of the Reactor Building, and a portion of the main steam tunnel and has a free volume of 4,000,000 cubic feet.
HOPE CREEK 5-1 c,-.e
. -.,