ML16341F307
| ML16341F307 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 08/29/1989 |
| From: | Rood H Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| TAC-74365, TAC-74366, NUDOCS 8909080040 | |
| Download: ML16341F307 (86) | |
Text
August 29, 1989 DOCKET NOS.:
50-275 and 50-323 APPLICANT:
FACILITY'UBJECT:
PACIFIC GAS AND ELECTRIC COMPANY (PG&E)
DIABLO CANYON NUCLEAR POWER PLANT, UNITS 1
AND 2
SUMMARY
OF AUGUST 8, 1989 PUBLIC MEETING TO DISCUSS DELETION OF CYCLE-SPECIFIC PARAMETERS FROM THE DIABLO CANYON COMBINED TECHNICAL SPECIFICATIONS (TAC NOS. 74365 AND 74366)
On August 8, 1989 the NRC staff met with PG&E in Rockville Maryland to discuss.
a proposed amendment request by PG&E to delete certain cycle-specific parameters from the Diablo Canyon Technical Specifications (TS).
These parameters would be incorporated in a core operating limits report (COLR), as recommended by Generic Letter 88-16.
Attendees at the meeting are given in Enclosure 1.
At the meeting, PG&E presented the revised technical specifications and the core operating limits report that they propose to submit to the staff.
This material is given in Enclosure 2.
At the meeting, the staff made the following comments about the revised TS presented by PG&E.
(1)
The staff recommended that there should be a separate COLR for each unit, rather than a combined COLR.
Therefore, references to "the plant-specific document" and "plant operation" should be changed to "the unit-specific document",
and "unit operation".
(2)
The staff recommended that references to "limits" and "limits provided in the COLR" should be changed to "limits specified in the COLR.
(3)
The staff recommended that TS 6.9.1.8, "Core Operating Limits Report,"
include a list of the specific cycle-specific parameters deleted from the TS and included in the COLR.
The list should include the section of the revised TS that references each cycle-specific parameter shifted to the COLR.
original signed by Harry Rood
--8cy09P80040 890829 PDR ADOCK 0500027~
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Enclosures:
1.
Meeting Attendees 2.
Proposed TS Changes and Draft COLR Harry Rood, Senior Project Manager, Project Directorate V
Division of Reactor Projects - III, IV, V and Special Projects 8g /89 cc: w/enclosures
- see next page DRSP/PD5 D
HRood ton 08/gS/89 DISTRIBUTION
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 Augus t 29, 1989 DOCKET NOS.:
50-275 and 50-323 APPLICANT'ACILITY
'UBJECT:
PACIFIC GAS AND ELECTRIC COMPANY (PG&E)
DIABLO CANYON NUCLEAR POWER PLANT, UNITS 1
AND 2
SUMMARY
OF AUGUST 8, 1989 PUBLIC MEETING TO DISCUSS DELETION OF CYCLE-SPECIFIC PARAMETERS FROM THE DIABLO CANYON COMBINED TECHNICAL SPECIFICATIONS (TAC NOS. 74365 AND 74366)
On August 8, 1989 the NRC staff met with PG&E in Rockville Maryland to discuss a proposed amendment request by PG&E to delete certain cycle-specific parameters from the Diablo Canyon Technical Specifications (TS).
These parameters would be incorporated in a core operating limits report (COLR), as recomended by Generic Letter 88-16.
Attendees at the meeting are given in Enclosure 1.
At the meeting, PG&E presented the revised technical specifications and the core operating limits report that they propose to submit to the staff.
This material is given in.
At the meeting, the staff made the following comments about the revised TS presented by PG&E.
(1)
The staff recommended that there should be a separate COLR for each unit, rather than a combined COLR.
Therefor e, references to "the plant-specific document"
-and "plant operation" should be changed to "the unit-specific document",
and "unit operation".
(2)
The staff recommended that references to "limits" and "limits provided in the COLR" should be changed to "limits specified in the COLR.
(3)
The staff recommended that TS 6.9.1.8, "Core Operating Limits Report,"
include a list of the specific cycle-specific parameters deleted from the TS and included in the COLR.
The list should include the section of the
. revised TS that references each cycle-specific parameter shifted to the COLR.
Enclosures:
1.
Meeting Attendees 2.
Proposed TS Changes and Draft COLR cc: w/enclosures
- see next page Harry Rood, Senior Project Manager Project Directorate V
Division of Reactor Projects
- III, IV, V and Special Projects
C h
b Mr. J.
D. Shiffer Pacific Gas and Electric Company Diablo Canyon CC:
Richard F. Locke, Esq.
Pacific Gas 5 Electric Company Post Office Box 7442 San Francisco, California 94120 Ms. Sandra A. Silver 660 Granite Creek Road Santa Cruz, California 95065 Mr. Peter H. Kaufman Deputy Attorney General State of California 110 West A Street, Suite 700 San Diego, California 92101 Managing Editor
=The Count Tele ram Tribune o nson venue P. 0.
Box 112 San Luis Obispo, California 93406 Ms. Nancy Culver 192 Luneta Street San Luis Obispo, California 93401 Regional Administrator, Region V
U.S. Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek, California 94596 Mr. John Hickman Senior Health Physicist Environmental Radioactive Mgmt. Unit Environmental Management Branch State Department of Health Services 714 P Street, Room 616 Sacramento, California 95814 NRC Resident Inspector Diablo Canyon Nuclear Power Plant c/o U.S. Nuclear Regulatory Comnission P. 0.
Box 369 Avila Beach, California 93424 Bruce Norton, Esq.
c/o Richard F. Locke, Esq.
Pacific Gas and Electric Company Post Office Box 7442 San Francisco, California 94120 Dr.
R. B. Ferguson Sierra Club - Santa Lucia Chapter Rocky Canyon Star Route Creston, California 93432 Chairman San Luis Obispo County Board of Supervisors Room 270 County Government Center San Luis Obispo, California 93408 Michael M. Strumwasser, Esq.
Special Assistant Attorney General State of California Department of Justice 3580 Wilshire Boulevard, Room 800 Los Angeles, California 90010
P
ENCLOSURE 1
Attendees, Public Meeting on Removal of Cycle-Specific Parameters From the Diablo Canyon Technical Specifications August 8, 1989 NAME Kent D. Daschke Daniel Fieno Roger Johnson Barclay S.
Lew Harry Rood ORGANIZATION Westinghouse NRC/NRR/SRXB PG&E PGSE NRC/NRR/PDV
E gO T
D ft 1
ENCLOSURE 2
RLJ:lfs 08/04/89 Attachment A
IHPLEMENTATION OF A CORE QPERATING LIMITS REPORT IN ACCORDANCE HITH GENERIC LETTER 88-16 A.
DESCRIPTION OF CHANGES AND AHENDHENT REQUEST This license amendment request (LAR) proposes to revise the Diablo Canyon Units 1
and 2 Technical Specifications to implement a Core Operating Limits Report (COLR) in accordance with Generic Letter 88-16, "Removal of Cycle-Specific Parameter Limits From Technical Specifications".
The proposed Technical Specification (TS) changes are as follows:
l.
Definition 1.43, "CORE OPERATING LIMITS REPORT" was added in accordance with Generic Letter 88-16.
2.
TS 3/4.1.3.5, "Shutdown Rod Insertion Limit", was revised to delete the inse-tion limit requirement and reference the COLR.
This change is consistent with Generic Letter 88-16.
3.
TS 3/4,1.3.6, "Control Rod Insertion Limits" was revised to delete Figures 3.1-1a and 3.1-1b and reference the COLR.
To support this change the reference to these figures in TS 3/4.1.3.1, "Hoveable Control Assemblies",
was deleted and the COLR referenced.
These changes are consistent with Generic Letter 88-16.
4, TS 3.2.1, "Axial Flux Difference",
was revised to delete Figures 3.2-1a and 3.2-1b and reference the COLR.
These changes are consistent with Generic Letter 88-16.
5.
Surveillance Requirements (SR) 4.2.2.1,2.c.
and 4.2.2.2.e were revised to reference the COLR instead of the Peaking Factor Limit Report.
SR 4.2.2.1.2.f was revised to reference the COLR instead of Figure 3.2-la.
The, Bases were revised to reflect this proposed change.
6.
TS 6.9.1.8, "Peaking Factor Limit Report" was deleted.
TS 6.9.1.8; "CORE OPERATING LIHITS REPORT" was added in accordance with Generic Letter 88-16.
The COLR will contain the information that was provided in the Peaking Factor Limit Report.
Since the COLR is required to be submitted to the NRC, it is no longer necessary to have a Peaking Factor Limit Report.
Changes to the TS are noted in the marked-up copy of the applicable TS (Attachment B).
A sample COLR for Unit 1 Cycle 4 and Unit 2 Cycle 3 is provided in Attachment C.
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C.
BACKGRQJND Generic Letter 88-16, "Removal of Cycle-Specific Parameter Limits from Technical Specifications" provides guidance for relocating cycle-specfflc parameters from the Technical Specifications so that future reload designs can be implemented ln accordance wfth 10 CFR 50.59.
The generic letter requires that the cycle-speclflc parameters be maintained ln a COLR and that the NRC be informed of changes to the COLR.
Any'changes to operating lfmlts will be made using approved NRC methodology for Diablo Canyon Power Plant (DCPP).
This change will not affect the operation or safety of OCPP Units 1 and 2, since the actions required to bo completed should a llmlt be exceeded wf 11 not be removed from the Tg.
The proposed TS changes include the removal of the Shutdown Rod Insertion l,fmft, the Cont~ol Rod Insertion Limits (Ffaures 3.l-la and 3.l-lb) and the Axial Flux Difference operational lfmlts (Figures 3.2-la and 3,2-lb) from the TS.
The proposed TS retain the Limiting Condition for Operatfon (LCO} wording and surveillance requirements bv referring to the specific limits which are provided to the NRC fn a CbLR fn accordance!with the proposed revisions to TS 6.9.1.8, This ls similar to the current TS which transmits cycle-specfffc values to the NRC via the Peaking Factor Limit Report ln the current TS 6.9,1,8, Relocation of these cycle-specific limits fs consistent with the guidance provided by the NRC fn Generic Letter 88-16, Removal of the limits from the TS will allow cycle-specific lfm'.:s to be implemented ln accordance with approved methodology fn a timely and cost effective mannor.
The format and content of the proposed TS changes havo been discussed fn a meeting 8 th the NRC and are consfstent with the new Standard Technfcal fpocfflcatfons for Hostfnghouse plants presently under review by the NRC;as a part of tho HERITS program.
In the future, PG&K expects to propose additional cycle spoclflc varfablos for lncluslon fn the COLR, a sample version which fs provided ln Attachment C.
JUSTIFICATION Implementing the guidance fn Generic Letter 88-16 will result fn a resource savings for PG&E and tho NRC associated with the review of LARs for changes to cycle-specific parameter limits.
Furthermore, implementation of this change will allow for cycle-specific parameter limit changes fn accordance with the referenced approved methodology of Section 6.9.1.8.
The relocation of the cycle-specific paramotor limits to tho COLR will allow for bptfmfzatfon of the designs to enhance operation and economics for each cjclo.
To support the optimized design for Unit 1 Cvcle 4 and to enable TS 3.2,2, Heat Flux Hot Channel Factor - Fq(z), to bo satisfied,'a more restrictive AFD lfmft fs required.
Implementation of a more restrictive AFO limit for Unft 1
and will avoid potential reactor 281 8S/M K/2
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AclJ pv r l1 slcD 1B 12789878 Fs 84 Draft 1
RLJ: lfs 08/04/89 power deraffnfI during the initial par t of Cycle 4 operatfon, Accordingly, PGhE bel1evos the NRC review and approval of this LAR should be given a high prior 1ty to ensure 1ssuance of a license amendment py December 1,
1989, to assure fts effectiveness prior to Unit 1 restart scheduled fn m1d-December 1989.
Sfmflar lfcense amendments
'have been issued in 1989 for Oconoo, Byron/Brafdwood, Hfllstone, '.and Brunswick.
- Also, a
COLR LAR for Shearon Harris fs presently dnder review by the NRC.
SAFETY EVA4UATION The relocation of the cycle-spoc1ffc parameters does not affect the operat1on of DCPP Un1ts 1 and 2.
The same actions will be taken when a
limit is exceeded as required by the present TS.
Revisions to the COLR will be made in accordance with 10 CFA 50.59 and the HRC will be notff1ed oi'll revisions in accordance with TS 6.9.1.8.
All rev1sfons to the COL will be based on NRC approved Iethodolog1es.
The proposed rev1sfon to the TS s1mply revfses the method by which changes to 'the cycle-specific parameter 11mfts can be requested and fmplementeg.
Revisions to the shutdown and control rod insertion 11m1ts wi 11 be based on the Hostfnghouse methodology previously reviewed and approved by the NRC and described fn HCAP-9272-P-A, "Hestfnghouse Reload Safety Evafuatfon Hethodology".
The AFD limits will be provided 1n accordance !with Hestfnghouse methodology previously revfewed and approved by the NRC and described fn H58-10216-P-A, "Rolaxatfon of Constant Axial Offset Control/F0 Surveillance Technical Snecfficat1on";
HCAP-9272-p-h, "Hestfnghouse Reload Safety Evaluation Hethodoloay";
and HCAP-8385, I"Power Distribution Control and Load Followfno Procedures".
Calculat1n the cycle-specific parameter limits fn accor8anco w1th an approved N
C methodology ensures the limits are consistent with the applicable rsafoty analyses addressed 1n tho DCPP FSAR Update.
In
- addition, TnS 6e9,1.8 1s revised to require tho limits bo maintained fn accordance.with those generated us1ng the approved methodology.
I As dSscussfd Sn thSs submSttal, there Ss reasonab'le assurance that the TS changes associated with relocating cycle-spec1ffc parameters out of the TS will not adversely affect tho health and safety of the publfc.
NO SIGNIFICANT HAZARDS EVALUATION PM E has oyaluated tho hazard consfderatfons 1nvolvod with the proposed amendment,:focusing on the three standards set fo~th in 10 CFR 50.92(c) as quoted IIelow:
The eossessjion may make SSnal determ)natSon, pursuant to the procedures fn 50.91, that a proposed amendment to an operating license fot a fac1lity licensed under 50,21(b) or 50.22 or for a testfnq fa)fifty 1nvolves no sfgnff1cant hazards consideration, ff operation Of the facility in accordance with the proposed amendment should'ot; 2818S/00 K/3
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6 Draft 1
RLJ:1 fs 08/04/89 (1)
Involve a significant increase ln the probability or consequences of an accident previously evaluated; or (2)
Create the possibility of a new or different kind of accident from any accident previously evaluated; or (3)
Involve a significant reduction ln a margin of safety.
The following evaluation ls provided for the three categories of the significant hazards consideration standards.
1.
Does the change involve a significant increase ln the probability or consequences of an accident previously evaluated?
The shutdown rod insertion limits, the control rod insertion limits and the AFD operational limits of the TS are cycle-specific parameters.
This LAR ls administrative ln nature and proposes to relocate these parameter limits to the COLR.
Eliminating the Peaking Factor Limit Report and placing the contents ln the COLR is an administrative change.
The removal of the cycle-specific parameters from the TS has no influence or impact on the probability or consequences of a previously evaluated accident.
The cycle-specific parameter limits, although not ln the TS, will be maintained via the DCPP TS and the COLR.
The proposed amendment still requires the same action to be taken when or lf limits are exceeded as ls required by the current TS.
Future reloads will be evaluated using NRC approved methodologies and will be examined per the requirements of 10 CFR 50.59.
Therefore, the proposed changes do not involve a significant increase ln the probability or consequences of an accident previously evaluated.
2.
Does the change create the possibility of a new or dlffere'nt kind of accident from any accident previously evaluated?
There ls no physical alteration to any plant system, nor ls there a
change ln the method by which any safety related system performs its function.
As stated
- above, the proposed change ls administrative ln nature.
Therefore, the proposed changes do not create the posslblllty of a new or different kInd of accident from any accident previously evaluated.
3.
Does the change involve a significant reduction tn a margin of safety?
The margin of safety ls not affected by the removal of cycle-specific parameter limits from the TS.
The proposed amendment still requires operation within the core limits as determined from the HRC approved reload design methodologies.
Appropriate actions will continue to be taken lf limits. are violated.
The development 2818S/00 K/4
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of the 11m1ts for future reloads vill cont1nue to conform to those methods descr1bed 1n HRC approved documentat1on.
In add1t1on, each future reload v111 Involve a 10 CFR 50.59 rev1ev.
Therefore, the proposed changes do not 1nvolve a s1gn1f1cant reduct1on 1n a marg1n of safety.
HO SIGNIFICANT HAZARDS CONSIDERATIOH DETEiNIHATIOH In conclus1on, based on the above evaluat1on, PGKE subm1ts that the act1v1t1es assoc1ated w1th th1s LAR sat1sfy the no s1gn1f1cant hazards cons1deratlon standards of 10 CFR 50.92(c) and, accord1ngly, a no s1gn1f1cant hazards cons1derat1on f1nd1ng 1s 5ust1f1ed.
EXVIROHHEHTAL EVALUATION PGhE has evaluated the proposed change and determ1ned that the change does not 1nvolve (1) a s1gn1f1cant hazards cons1derat1on, (11) a s1gn1f1cant change 1n the types or s1gn1f1cant 1ncrease 1n the amounts of any effluents that may be released offs1te.'r (111) a s1gn1f1cant 1ncrease 1n 1nd1v1dual or cumulat1ve occupat1onal rad1at1on exposure.
Accord1ngly, the proposed changes meet the el1g1b111ty cr1ter1on for categor1cal exclus1on set forth 1n 10 CFR 51.22(c)(9).
Therefore, pursuant to 10 CFR 51.22(b),
an env1ronmental assessment of the proposed changes 1s not requ1red.
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12789878 P, 85 Drift 1 RLJ:1 ft OS/04/89 Attachment 8
HARKEO-UP TECHNICAL SPECIFICATION PAGES 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 3/4 8 3/4 1-22 1-23 1-24 21 2~2 2&3 2~7 2-8 2-12 2-5 11 V
Il-7 3/4 1-15 3/4 1-16 3/4 21 V
xx11 1-7 3/4 1-15 3/4 1-16 3/4 1-21 3/4 1-22 3/4 2
1 3/4 2-2 3/4 2-3 3/4 2>>7 3/4 2-8 3/4 2-12 B 3/4 2-5 6-20 2818S/00 K/6
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INDEX DEFINITIONS SECTION DEFINITIONS (Continued) lo31 SHUTDOWN MARGINe ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
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1.32 SITE BOUNDARY............
1.33 SLAVE RELAY TEST...
- l. 34 SOLIDIFICATION.......
PAGE 1-6 1-6 1-6 1"6 1.35 SOURCE CHECK.......
1.36 STAGGERED TEST BASIS....,..............
1.37 THERMAL POWER..
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1-6 1-6 1-7 1.38 TRIP ACTUATING DEVICE OPERATIONAL TEST.........................,.
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- 1. 39 UNIDENTIFIED LEAKAGE.
1.40 UNRESTRICTED AREA...
1.41 VENTILATION EXHAUST TREATMENT SYSTEM..
,42 VENTING........
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1-7 1-7 1-7 1-7 TABLE 1. 1 FREQUENCY NOTATION................,..
TABLE 1.2 OPERATIONAL MODES..............,...........
1-8 l.4s c <<e.
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DIABLO CANYON - UNITS 1 h 2
C.
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INDEX LIM171NG CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECT I OH 3/4.1 REACTIVITY COHTROL SYSTEHS (CnnIInuod)
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3/4. 2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE............................".--.
3/4 2-1 DEL.61/0 dA e g
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3/4,2.2 HEAT FLUX HOT CHANNEL FACTOR-FQ(Z)................ ~....
FIGURE 3.2-2 K(Z) - NORMALIZED F (Z) AS A FUNCTION OF CORE Q
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3/4.2.3 RCS FLOV RATE AHD NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR.........................-...........
3/4 2-3 3/4 2-5 3/4 2-t3 3/4 2-13 FIGURE 3.2-3a RCS TOTAL FLOVRATE VERSUS AfteT) ~
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3/4.2,5=
DNB PARAMETERSoo TABLE 3. 2-1 DNB PARAMETERS..............
R (UNIT 1 Cycle 4 and
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R (UHIT 2 Cycle 3)......
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TABLE 3. 3-1 REACTOR TRIP SYSTEM IHSTRUMEHTATION.................
TABLE 3.3-2 REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMFS..
TABLE 4. 3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE R EQUIREMEHTSo ~ ~ ~ ~ ~ ~ ~ ~ i ~ ~ ~ ~ ~ ~ ~ ~
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TABLE 3.3-3 EHGIHEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION..........,..........,....,........
3/4 3-1 3/4 3-2 3/4 3-8 3/4 3-10 3/4 3-14 3/4 3-15 DIABLO CANYON - UNITS 1 4 2
V Amendment Hos. 37 and 36 Effective at end of Unit 1 Cycle 3
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INOEX mIHISTRATIVE CONTROLS SECTION
- 6. 5 REVIEW AHD AUDIT Continued PAGE 6.5.2 GENERAL OFFICE NUCLEAR PLANT REVIEW AND AUDIT CQSITTEE (GONPRAC)
Functiono
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R 6-9 6-10 6 10 6-10 6-10 6-10 6-10 6 11 6-12 6.6 REPORTABLE EVENT ACTION.........................................,
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- 6. I SAFETY LIMIT VIOLATIOH...........................................
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- 6. 8 'ROCEDURES AND PROGRAHS..........................................
6.9 REPORTING RE UIREMENTS 6-13
- 6. 9.1 ROUTINE REPORTS...............................................,
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Annual Radiological Enviroreental Opef ating Report..
Seaiannual Radioactive Effluent Release Report......
monthly Operating Report............................
CORE OPERATINb I INES
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- 6. 11 RADIATION PROTECTION PROGRAM...................,,,..............
6-22
- 6. 12 HIGH RADIATIONAREA...................................,.........
6-22 DIABLO CANYON - UNITS 1 4 2 xxii Amendment, Nos. 37 and 36 Effective at end of Unit 1 Cycle 3
DEFINITIONS THERMAL POWER 1.37 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
TRIP ACTUATING DEVICE OPERATIONAL TEST 1.38 A TRIP ACTUATING DEVICE OPERATIONAL TEST shall consist of operating the Trip Actuating Device and verifying OPERABILITY of alarm, interlock and/or trip functions.
The TRIP ACTUATING DEVICE OPERATIONAL TEST shall include adjustment, as necessary, of the Trip Actuating Device such that it actuates at the required Setpoint within the required accuracy.
UNIDENTIFIED LEAKAGE 1.39 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE or CONTROLLED LEAKAGE, UNRESTRICTED AREA 1.40 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.
VENTILATION EXHAUST TREATMENT SYSTEM l.41 A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radioiodine or radioactiv'e material in par-ticulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the'elease to the environment.
Such a system is not considered to have any effect on noble gas effluents.
Engineered Safety Features Atmospheric Cleanup Systems are not normally considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.
VENTING 1.42 VENTING shall be the controlled process of 'discharging air or gas from a confinement to maintain temperature,
- pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING,
- Vent, used in system
- names, does not imply a VENTING process.
~i~>~+
DIABLO CANYON " UNITS 1 8
2
l
~
F
GP-&~ Ii<L LIMIT I Cf'r>AT I.45 I Qe QXC OPQWTINb i IHI I5
!ZAN ~OPT IS HlE ~- Sect(IC dc<qmeni'hcl-provIdw core ~rat.i@9 JIrnifs for IhE Current.
a iong reload epee Tnese crrde - Speciel r core oper aking ln h shall be dArmned /or <0~ f<
Q cgQ5 Gccordonce MIJN 5pci(ical-ion I A.lA',
OperGJ-I'o~ uk',n these operah'nII Iierls r>
addressed in rndNr4ual spec 0icahiom
r r
pgr94/i~ Gg'GpE PE~ATO2Y CCVPL lthlC RK 9'2&Ba177 P. P2 REACTIY TY NT L SYST S
- i. 1.3 IC)VAS E CONTROL ASS:N IES LIHIT NG CONDITION FOR OPERAT ON
- 3. 1.3. 1 All full-length shutdown and control rods shall be'OPERABLE and positioned. within t 12 steps (indicated position) of the1r group demand pos 1 tion.
~ACT DN:
ao b.
With one or more full-length rods inoperable due to being immovable as a result of excessive fricCion or aechanical interference or known to be untrippable, determine that the SHUTtNNH HARGIN requirement of Specification 3.1.1.1 1s satisfied within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
11th one full-length rod trippable but inoperable due to causes othe~
than addressed by ACTION a.,
- above, or a<saligned from its group demand height by more than 4 12 steps (1ndicated pos1tion),
PSKR OPERATION aay continue provided that within 1 hour:
The rod is restored to OPERABLE status within the above aligneent requirements, or The rod is declared inoperable and the rewainder of the rods in the group with the inoperable rod are aligned to w1thin a 12 steps of the inoperable rod while maintaining the rod sequence and insertion limits The THERMAL PMER level shall be restr 1cted pursuant to Specification 3. 1.3.6 dur<na subseouent operation, or Speci flMjol8.l.5.9 The rod is declared
<noperable and the SHUTDStM MARGIN requirement of Specification 3.1.1.1 is satisfied.
POMER OPERATIOH Nay then continue provided Chat:
a}
A reevaluation of each accident analysis of Table 3.1-1 is performed within 5 days; this reevaluation shall confirw that the previously analyzed results of these accidents rewain valid for the duration of operation under these condi t 1 ons; b)
THE SHUTDOWN HARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />;
~See Special Test Exceptions Specifications 3.10.2 and 3.10.3.
OIASLO CANYON - UNITS 1 4 2 3/4 1-15
l l
~~r1989 89 RRE REGLLATCRY~ IPt4.
987 1268 177 P. 8 REACT?YITY'TROL TE S
L MITING CONDITION F R OPERAT Off ACTION Con fnued c)
A power dfstr fbutfon map fs obtafned from the movable fncore detectors and F~(Z) and F~ are verfffed to be tf wfthfn thefr lf@fts wfthfn 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; and d)
The THERMAL KWER level fs reduced to less than or equal to 75K of RATED THERMAL POWER wfthfn the next hour and wfth1n the followfng 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the Hfgh Neutron Flux Trfp Setpofnt fs reduced to less than or equal to b% of RATED THERMAL POMN.
fifth more than one rod tr fppabl ~ but fnoperabl ~ due to causes other than addressed by ACTION a above, POWER OPERATION lay contfnue provfded that:
+ 5qecibicaiiog 9.I.5 V.
1,
'Nthfn 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, the remafnder of the rods fn the bank(s) wfth the 1noperable rods ar>> elfgned to wfthfn k 12 steps of the fnoperabl ~ rods whfle ma1ntafnfng the rod sequence and fnsert1on THERMAL P(NKR level shall be restrfcted pursuant to Specfffcatfon 3.1,3.6 durfng subsequent operatfon, and 2.
The fnoperable rods are restored to OPERABLE status wfthfn 72
- hours, d,
fifth sore than one rod mfsalfgned from fts group demand posftfon by sere than a 12 steps (fndfcated posftfon),
be fn HOT STANDBY wfthfn 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE RE UIREHENTS 4.1.3. 1. 1 The posftfon of each full-length rod shall be determfned to be wfthfn the group deaand lfaft by verffyfnp the fndfvfdual rod posft1ons at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except durfng tfee fntervals when the Rod Posftfon Devfatfon Monftor fs fnoperable, then verffy the group posftfons at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
4, 1.3. 1.2 Each full-length rod not fully fnserted fn the core shall be deter-mfned to be OPERABLE by movement of at least 10 steps fn any one dfrectfon at least once per 31 days.
DIABLO CANYON - UNITS 1 4 2 3/4 1 16
I
88~r1989 ER:,
RRE RERLATCRY CCePL
> FHC 8855
~
12S891?7 P. 84 EACTIVITY CONTROL SYSTENS
&uTOOW ROD I~SERTIO~ L 8 T LIHITIHG CO ITION FOR OPERAT OH f)~;~ t~ ~ccLt i058'Hoh Qb ~ecifl'ec(
3.l.3.5 All shutdown rods shall be
>n ~ht CfQ ~RN]Hb UNrt5 %ART, PLICAB LITY:
MOOES 1~ Ind 2 t.
ggON:
, Q. COLE~
j~pfgf~~ 8R ilail'ffQfll>N~"
V)th a lax(am of one shutdown rod except for surveillance test)ng pursuantito
.$ aclffcatfon 4.1.3.1.2, Qthfn 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either:
[esto' r6 4 @<pip a I'~(
L a.
or b.
Declare the rod to be inoperable and app1y Spec)fkcatfon 3.1.3.l.
tI'URVEILLANCERE UI REAGENTS
- 4. 1.3.5 Each shutdown ro4 shall be detemkoed to.he taint Nc insertion linis~.x~z. ~ M t
f a.
Mfthfn 15 minutes prior to withdrawal of any rods
$ n Control Banks A, $,
C or D during an approach to reactor criticality, and b.
At 1east once per Q hours thereafter.
I w,, s,p <,sp<rt u I.M,C sa.so.L NM<th K ff greater than or equal to 1.
DIASLO CANYON - UNITS 1 4 2 3l4 1-Z1 Amendment Nos,4O and 39 June 7, I98S
~
4 r ~
,, RRE REGLLATOZY~ IFHC MS5 II
~
Iy I
. REACTIV TY CONTROL, SYSTEMS CONTROL ROD INSERTION LIHITS LIMITING CONDITION FOR OPERATION gq)ed in }he 3.1.3.6 The control banks shall be limited fn physical fnsertfon'es Q~ ()P6KPliNr WHI'f5 LbR:TE COL) A APPLICABILITY:
MODES P and 29.
ACTION:
With the control banks inserted beyond the eleve insertion lfefts, except for surveillance testfng pursuant to Specification 4. 1.3.1.2:
e.
Restore the control banks to within the lfmfts within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, or b.
Reduce THERHAL POWER wIthin 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to less than or equal to that I
\\
I EEEEE IEEEEEE PP E
I I
Ey I
I"II c.
Be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE RE UIREHEKTS
- 4. 1.3.6 The position of each control bank shall be determined Co be within the insertion lfeits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except durfnp tfme fntervals when the rod insertion lfaft tsonitor fs inoperable, then verify the individual rod positions at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
"See Special Test Exceptions Specifications
- 3. 10,2 and 3. 10.3.
fifth K ff greater than or equal to 1.
DIABLO CANYON - UNITS 1 & 2 3/4 1-22
I I
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- MMW ~
~
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~
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6 220 Dc.~c~
(F vl1y withdrawn, 226 stops)
BANK A 6 S BANKS A.B. 5 C O.61.228) 200 xO 180 I-O) 180 QL,.
140 tQ 120 I-hC 100 Cl 80 ClQK Bb (0.0,98)
ANK C BANK D (1.0, 188) 40 20 0
(0. 14.0)
THERMAL tOWER LIMITED TO A MAXtLllJMOc XQ'L OF AATEO TKERMAL tOWER BY HEUTAOM FLVX ROWER AAHOE TlttP 0
CO 2O SO 40 6O eO 7O soli 9O 1O0 PERCENT OF RATED THERMAL P ONER FIGURE 3.1-1b ROO BANK INSERTION LIMITS YERSUS THERMAL POWER (UNIT 2)
DIABLO CANYON - UNITS 1 8 2 3/4.1-24 Amendment Has. "
June 7, l989
I 0
1
~
~,
4
%$%R 57 UT N L I 5 4..
I FN F
%HE 17 NC DTI NS F
P RATION
$.2.l The fndfcated AXIAL FLttX DIFFERENCE (AFD} shall be aafntafned Qthfn the
. llanos ~W in -4he.
CKE OVEMiNb Liter&
ZT (CNR)
APPL LITY:
NDK l ASOVE $0 PERCENT RATED THKNNL~
$QJP:
Wth the fndfceted AXIAL FLUX DIFFERENCE outsfde of the 1.
Kfther restore the fndfcated AFQ to vfthfn the lfifts vfthfn 15 efnutes, or 2,
Reduce THERMAL POWER to less than SN o( RATED THENAL POWER v<thfn 30 Ifnutes and reduce the Pover Range Neutron Flux Hfgh Trfp setpofnts ta less than or equal to 55 percent of RATED THERHAL POWER vfthfn the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
b.
THERNAL POWER shall not be fncreased above RC of RATED THECAL POwER unless the fndfcated AFD fs vfthfn th>>
lfafts. peedd in,ee CGA.,
SURVE1LLANCE RE UIREHEttTS 4.2.1.1 The fndfcated AXIAL FLUX DIFFERENCE shall, be determfned to be vfthfn its lka<ts durfng POWER OPERATION above 50 percent of RATED THERMAL POWER by:
~,
Honftorfng the fndfcated AFD for each OPERABLE excore channel:
1.
At least once per 7 days'vhen the AFD Nonftor Alare fs OPERABLE, and 2.
At 1east once per hour vhen the AFD Nanftor Alare
$ s fnoperable.
- 4. 2.l.2 The fndfcated AFD shall be consfdered outsfde of fts lfafts vhen et least 2 OPERABLK excore channels are fnd<catfng the AFD to be outsfde the lfifts.
'See Specfal Test Kxceptfons Specfffcatfon 3.l0.2 OIABLO CANYON VNITS 1 4 2 3/4 2-1 Amendment Hos. >>>>4 3
Kffectfve at end of Unft l 4'cle
~
~
~
~
, ~
P AB
, ~
'I20 6
DELVE UNITS l L 2 CYCLE 4 AND AFTER'00 i@ACCEPTABLE DPERAIIDN maCCEPTABcE
~ER4TICN BD 4XX 60 D
CY 40 ACCEPTABLE OPERATION
(
V 50) 20 l
I I
I 0
-40
-30 20 l0 0
$ 0 20 30 "60 40 50 60 F'X QIF'f'ERENCE (AI)X FlGURE 3.2;W AXlAL FLUX DIFFEREHCE LlHITS AS A FUHCTIOH OF RATED THERHAL POWER (UHITS 1 AHD 2 CYCLE 4 AHD AFTER)
DIABLO CAHVOH - NITS 1 4 2 3/4 2-2 Aeendmcnt Noj, 37 and 36 Effective at end of Un)t 1 Cyc1e 3
I
~
~
UNIT 2 CYCLE 3 120
]00-CEPTABLE QPERAT 1QN UNACCEPTABLE OPERATION 80 6o-Cl
.o ACCEP, ABlE OPERATlON (2
20 I
I 50
-40 30
-20 lo 0
lo 20 FLUX DlFFERENCE CJhl)X 40 50 60 FIGURE 3.2-Q AXIAL FLUX DIFFEREHCE LIMITS AS A FUHCTIOH OF RATED THECAL PSKR (UHIT 2 CYCLE 3)
DIABLO CAHYOH - NITS 1 4 2 3/i 2-3 ANendment Hos.
37 and Effectfva at end of Un)t 1 Cyclt 3 1I
I
~ I P
e 4
88/84/1989 89:
PCS RERLATCRY~ 1 PtC 885 987 12689177 P. 87 P
R 1T IUTON 8
S URYE1LLAHCE RE 1R MENTS 4.2.2.1.1 The pr'visions of Specification 4.0.4 are not applicable.
4.2.2.1.2 F<(z) shall be evaluated to determine
$f F~(z) ts Hthin Its 14]ts by:
ae e.
llsfng the Noveable encore 'detectors to obtain a pear distribu-tion Nap at any THERNL P(NER greater than Q of RATKO THElNhL PAAR.
)ncreasing the aeasured Fg(z) colponent of the pcwer d1stribution up by 3X to account for aanufacturing tolerances and further in-creasing the value by 5X to account for oessureaent uncertainties.
Satisfying the following relationship:
F~(z} c
.i5 x K z for P > Oe5
'K x
z F~(t) c
.45 x K t for O e 0.5 z
x Acre F~(z} fs the aeasured F~(z} increased by the allowances for aanufacturing tolerance>>
and Ncasurelent uncertainty, 2.i5 is the F~ i)lit, K(z} is given
$ n Figure 3.2.2,'
fs the relative THERMAL PSKR, and M(z) Is the cycle dependent function that
-accounts for power distribution transients encountered during 3
p I
TM f U
I f
h 4eak4&A P
SD itl I
L
.Lag'easuring F~(z} according to the follcnring schedule:
1.
Upon achieving equil (brogue conditions after excecdina by 2(C or Nore of RATED THERMAL P(WER, the THKRNL PSCk at which f~(z} vas last deters]ned,~
or 2,
lt least once per 31 Effective full Parer Days (fFPO),
A<chever occurs first.
Vith atasurelents
)ndicating
~ex(sw F>(t )
over'
~z hee (ntreeeed e(nte the Orev(oue otter(net(on ot F~(t)
~(ther of the foller<ng actions shall be taken:
'uring po~cr escalation at the beginning of each cycle, pover level any be
<ncreascd unti l a powr level for ertcnded operation has been achieved and a po~r distribution Nap obtained.
DIA8LD CAHYON - NiTS 1 C 2 3/i 2-1 heendotnt los. 37 and 36 Effective at arum ~e ))~4(
s r.,is
pl s ~
QQzg4zlgpg Q9:~ PRE RE~TCPY ~t~
. BQ-5 e7 l2SC8177 P.QS v
R I TRISUT OH 1
SURV I LANCE NE 0
MT ontfnMed 2) p~(!) shall be tncreased hy 2% oven that spectate
'ln Specfffcatfon 4.2.2.l.R.c, or F~(z) shall he srasondit
'toast once per 1 Ep~ >>tcolic@ 8.8, I OIASLO CANYON - VN?TS 1 4 2
.. 3/4 X-e
~n4eent
@os, 37 and eg Effectfve at end of Vnft 1 Cycle 3
0,
~
~ 4
.J I
J
POMER DISTRIBUTION LIHITS SURVEILLANCE RE UIREHENTS Continued c.
2.
Mhen the F
is less than or equal to the (F
) limit for C
RTP the appropriate measured core plane, additional p~r distribution mps shall be takin and F
coapared to Fxy and F
at least once per 31 EFPO.
L The F liait for RATED THERHAL PSKR (F
) shall be provided for all core planes containing Bank "0" control rods and all unrodded core planes in per Specification 6.9.1.8..&e QXc OP('XA<<Nb N'(X'8 P'A3PT f.
The F limits of Specification 4,2.2.2.2e.,
- above, are not applicable in the follming core plane regions as measured in percent of core height from the bottom of the fuel:
1.
L~r core region from 0 to 15K, inclusive, 2.
Upper core region from 85 to lOOX inclusive, 3.
Grid plane regions at 17.8 i 2X, 32,1 i ZL', 46.4 a 2X, 60.6 a ZL and 74.9 i 2X, inclusive, and 4.
Core plane regions within k 2X of core height (a 2.88 inches) about the bank demand position of the Bank "D" control rods.
g.
Mith F exceeding F
, the effects of F on F (Z) shall be evaluated to determine if Fq(Z) is vithi its 1 mits.
4.2.2.2.3 Vhen F~(Z) is measured pursuant to Specification 4.10.2.2, an ov ral1 Neasured F (Z) shall be obtained from pcwer distribution aap and increased by 3X to account for Nanufacturing tolerances and further increased by 5X to account for measurement uncertainty.
DIABLO CANYON - UNITS 1 8 2 3(4 2-12 Amendment Hos. 37 and 36 Effective at en4 of Unit 1 Cycle 3
~
~ g
POWER DISTRIBUTION LIMITS BASES HEAT FLUX KOT CHANNEL FACTOR and RCS FLOWRATE and HUCLEAR ENTKALPY RISE KQT NN ont)nue Mhcn an F~ eeasureaent is taken, an allowance for both experiaental error end aanufacturing tolerance aust be aade.
An.allowance of 5X <s appropriate for a full core sap taken with the incore detector flux aapping system and a
3X allowance
$ s appropriate for aanufacturing tolerance.
lien RCS flow rate and F~ are aeasured, no additional allowances are H
necessary prior to comparison with the limits of Figures 3.2-3a, b and c.
measurement errors of 2.4X for Units 1 and 2 Cycle 4 and after, and 3.5X for Unit 2 Cycle 3 for RCS total flow rate and 4X for F~ have been allowed for in deteraination of the design DNBR values.
For Units 1 and 2 Cycle 4 and after, the 4X is applied to the DNBR limit.
For Unit 2 Cycle 3, the 4X is applied.to HF~.
The 12-hour periodic surveillance of indicated RCS flow $ s sufficient to detect only flow degradation which could lead to operation outside the acceptable region of operation shown on Figures 3.2-3a, b, and c.
For Unit 2 Cycle 3, the Peaking Factor, F(Z), is measured periodically xy to provide additionai assurance that the Hot Channel Fac'.".r, Fii(Z), resus~in within its limit.
The F
limit for RATED THERMAL POWER (F
) as d in xy xy the~
per Specification 6.9.1e8 was deterlined from expected power control maneuvers over the full range of burnup conditions in the core.
~ ('KL GFc,P/a"a it a S Ls t4if' P~
For Units 1 and 2 Cycle 4 and after, the hot channel factor F (z) is measured periodically and increased by a cycle and height dependent power factor appropriate to RAOC operation, M(z), to provide assurance that the limit on the hot chan el factor F~(z) is act.
N(z) accounts for the effects of normal operation transients a'nd was deterlined from expected power control Naneuvers over the full range of burnup conditions in the core.
The M(z) function for normal operation is
$ n the fea~~acto~eit-Report-per Specification 6.9.1.8.
~
C<ruC, OPLVJO ih1b LIMITS P~KC I 3/4.'2.4 UADRAHT POWER TILT RATIO The QUADRANT POWER TILT RATIO liait assures that the radial power distri-bution satisfies the design values used in the power capability analysis.
Radial power distribution aeasurements are aade during startup testing and periodically during power operation.
The limit of 1.02 at which corrective action
$ s required provides DHB and linear heat generation rate protection with x-y plane power tilts.
The limit o'.
- 1. 02 was selected to provide an allowance for the uncertainty associated with the indicated power tilt.
DIABLO CANYON - UNITS 1 4 2 B 3/4 2-5 Amendment Kos.37and Effective at end of Unit 1 Cycle 3
l
+t
ADHINISTRATIVE COHTROLS SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator of the kRC Regional Office within the time period specified for'ach report.
- 6. l0 RECORD RETEHTIOH In addition to the applicable record retention requirelents of Title 10, Code of Federal Regulations, the following records shall be retained for at least the ainiium period indicated.
- 6. 10.1 The folloving records shall be retained for at least 5 years:
a.
Records and logs of unit operation covering time interval at each pover.
1cvcl; b.
Records and logs of principal aaintenance activities, inspections, repair and replaceaent of principal items of cquipaent related to nuclear safety; c.
All REPORTASLE EVENTS; CAP-8385 "Pouergtstrtbutt Control and Load Fol'IALng P durhs. i CAP-9272-A "lgtestinghouse Re ad,Safet Evalu'ation Hetlodolo
" and QP-10215;P-A "Relaxation of nstant 4ial Offset Conti o1/F urve)%lance Technica1 Specification."
Q DIABLO CANYON - UNITS 1 8 2 6-20 Amendment Hos. 37 and 36 Effective at end of Unit 1 Cycle 3 KNTHLY OPERATING REPORT 6.9.1.7 Routine reports of operating statistics and shutdown experience, includ-ing documentation of all challenges and failures to the PORVs or safety valves, shall be submitted on a aonthly basis to the Director, Office of Resource Manage-
- mentt, U.S. Kuclcar Regulatory Coceission, Vashington, D.C. 20555, vith a copy to the Regional Administrator of the Regional Office of thc KRC, te later than the 15th of each aonth following the calendar sonth covered by the rcport.
PEAKING FACTOR LIHIT REPORT 6.9.
8 The F
liaits for RATED THERNAL'PSKR (F
) shall rovided to the NRC n accordance erich 10 CFR 50.8 for all core plane ontatntng Bank '0" control-rods..and all unrodded core planes at least 60+ays yrior to tach cycle initial criticality.
In the event that the Qait vould be submitted at some other tile.,during core life, it vill beMubRittcd 60 days prior to the date the limit vould becoee effective up1css othervise exempted by the CoaNLission.
This report is not require~dor the initial cycle.
The N(z) function for Load Follow operation shall be established for at least each reload core and shall be aagMined available at the plant.
The limits shall be established and impIemented on a time scale consistent vith normal Iprocedural changes.
The ymlytical aethods used to generate the V(z} function
,shall be those prcviouspy reviewed and approved by the HRC.~ If changes to
'these methods are deemed necessary they will be evaluated in accordance vith
- 10 CFR 50.59 and suSmitted to the NRC for review and approval prior to their
- use if the changt is determined to involve an unrevicwed safety question or if such a cheque uould requtre amendment of prevtously submitted documentation.
'A reportwontaining the M(z) function, as a function of core height (and burnupAf applicablc), shall be provided to the HRC in accordance vith 10 CFR 50.i vithin 30 days of their implementation.
r
'p v
vs "
Draft 1
RLJ:1 fs 08/04/89 INSERT A CORE OPERATING LIMITS REPORT (Q
6.9.1.8 Core operating limits shall be established and documented in the CORE OPERATING LIMITS Rgl%RT before each reload cycle or any remaining part of a reload cycle l.~)The analytical methods used to determine the core opera~tin Wmtts shall be those previously revieved and approved by the (ql'3 HCAP-10216-P-A, Relaxation of Constant ia Offset Control F
Surveillance Technical Specification, HCAP-9272-P-A, Hestinghouse Reload Safety Evaluation, Hethodol gy, md
('i> 'E~
HCAP-8385, Power Distribution Contro) a d
oad Following Proc4.duces.
I~yq (u
~~i The core operating limits shall be determined so that all applicable i
limits (e.g.,
fuel thermal-mechanical limits, core thermal-hydraulic
- limits, ECCS limits, nuclear limits such as SHUTDOHN MARGIN, and
[
ii transient and accident analysis limits) of the safety analysis are met.
Qcli The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements
- thereto, shall be provided, upon issuance for each reload cycle, to the NRC Document Control Desk, with copies to the Regional Administrator and Resident Inspector.
s 2818S/00 K/7
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Draft 1
RLD: 1 fs 08/04/89 Attachment C
Sample Core Operating L1m)ts Report 2818S/00 K/8
~
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Draft 1
RLJ:1fs 08/04/89 Diablo Canyon Unit 1 Cycle 4 CORE OPERATING LIHITS REPORT Revl sion A
August 10, 1989 2818S/00 K/9
l E.
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1 41597 18 12789878 P. 86 Draft 1
RLJ:)fs 08/04/89
'1.0 CORE OPERATIHII LIMITS REPORT This Core Operatlnj LIlslts Report (COLR) for Diablo Canyon Unit 1 Cycle e~=
has Ibeen prepared 1n accordance x1th the requ1rements of Techn1ca Spec1f1cgt1on 6.9.1.8, I
The Techn1cal Spec1f1cat1ons affected by th1s report are 11sted belox:
3/4.1,3e5 Shutdoxn Rod
? nsert1on L1I1t 3/4 1.3.6 Control Rod Insertton L1m1t 3/4.2.1 Aj1al Flux 01 fference 3/4.2.2 Hjat Flux Hot Channel Factor - Fq(z) (Surve1llance Requ1rements only?
~~~bet<
ce
- 2. 0 OPERATING LIHtTS The cycle-spec1f1c parameter 11m1ts for the spec1f1cat1ons 11sted 1n Sect1cn 1.0 are presented ln tlIe followlnp subsections.
These Ilwlts have been developed us1ng the NRC-approved methodolog1es spec1f1ed 1n Techn1cal Spec1f1cat1on 6.9.1.8.
Page 1 'of 11 2818 S/00 K/10
e e
k
Draft 1
RLJ:1fs 08/04/89 2.1 Shutdown Rod Insert1on L1m1 ts (Spec1f1cat1on 3/4.1.3.5) 2.1,1 The shutdown rods shall be w1thdrawn to at least 225 steps.
2.2 Control Rod Insert1on L1m1ts (Spec1f1cat1on 3/4.1.3.6) 2.2.1 The control rod banks shall be 11m1ted 1n phys1cal 1nsert1on as h
3 Flit eat,~
I 2.3 Ax1al Flux D1fference (Spec1f1cat1on 3/4.2.1) 2.3.l The AXIAL FLUX DIFFERENCE (AFD) L1m1ts for Un1t l Cycle 4 are prov1ded 1n F1gure~~
LRHB(~&
m s
or n
yc e
are 2.4 Heat Flux Hot Channel Factor - Fq(zl ~
2.4.1 The W(z) curves for RAOC operat1on prov1ded 1n F1gures ~ through
~i.=4 for Un1t l Cycle 4 are suff1c1ent to determ1ne the RAOC W(z) vh sus core he1ght for Cycle 4 burnups through the end of full power react1v1ty plus a power coastdown of up to 1000 HWD/HTU.
Spei1f1cat1on 3/4.2.2.2, 2.4.2 The Fx> limits for RATED THERHAL PDHER (FxvR~T < ii Figure 2.4-5 for Un1t 2 Cycle'3 are to be'iused to conf1rmQkat the heat flu channel factor FD(z> meets the limitawf Technical Specification
,3~2.2.2 fa the Surveillance rements of 4.2.2.2.2.e.
Page 2 of ll 2818S/00 K/11
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PGEE REBASITCRY~ IANC 8855 12689177 P. 84 U
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COLR for OtABLO CANYON UNIT I CYCLE 4 and UN?T 2 CYCLE 3 Pvtly withdrawn, R24 Itopo)
SANK A SANK A C I
- 0. 18,228 QANKS AI, 4 C 0.69 228 aoe X
Q 1eo I
18O aO.
140 Ql CO 120 100 C
80 C0 80 BA
- 0. 183 (0,44)
SANK C BANK D (1.0. 17 7) 20 0.20 0 THBtMAL10lVDI tPAJTCb TO A MAXMVMOF XO'L OF hATCO THDlMALO'OS Eh eY NRUThON FLVX aoWu hANOC ta>>
0 10 20 00 10 40 40 TO 80 00 100 PERCENT OF RATED THERMAL POWER I
Figure Sgsk Rod 8ank lnsertlon L1N1ts Versus Therlal Power (Unit 1)
Page
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REGAXiTCRC CCtFL 1 AHC 88S5 4(
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SANK A 4 I SANKS A.S, 4 0 Q.e1.22b 200 X0 1dQ sao aA.
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0 10 RO 00 40 50 00 70 00 90 100 PERCENT OF RATED THERMAL &0%FR F)gure':2-2 Rod Bank Insert)on L)mits Verius Thermal Power (Unit 2)
Page 4 of ll
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COD for OIA3LO CANYON UNIT I CYCLE 4 and UNIT 2 CYCLE 3
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CYCLE 4 VMCCar TMCa OtPATIQH 00) 9,
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Vn1t I Cycle 4 t4"i a
00'!Nr gun 5 j F)pure M-f Wf2) at 10000 $6/MTU 0
0 Page 9 of ll
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- Qntt 1 Cycle 4 SN Nh
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,'- m 88r88i1989 89:
PG 8,E NUC REG AFFAlRS 4159 18 12789878 P,81 Draft 1
RLJ:lfs 08/04/89 F1gure 2.4-5 01ablo Canyon Un1t 2 Cy le 3
L1m1ts for Rated Thermal Power
/
for Unrodded and Rodded Core Planes The Fxy 11 shall 5e:
2
~
These F y'(
factor Pg(
1ts for RATED THERMAL PONE wlth1n spec1f1ed core planes FxyRTP less than or equal to 1.84 for all core planes conta1n1ng bank'D" control rods, and
/
F>>RTP z 1.69 up to 30% core heIght, g 1.61 above 30'I of core he1ght from the bottom of the fuel for unrodded core planes.
I
)
11m1ts were used'to conf1rm that the heat flux hot channel
)
w111 be 11m1ted 'to Techn1cal Spec1f1cat1on 3,2.2,2.
Page ll of 11 2818S/00 K/20
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