ML17324A751
| ML17324A751 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/20/1986 |
| From: | Wiesemann R WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17324A745 | List: |
| References | |
| CAW-86-017, CAW-86-17, NUDOCS 8603200301 | |
| Download: ML17324A751 (69) | |
Text
Box 355 Westinghouse Water Reactor Pittsburgh Pennsytvania 15230 0355 Electric Corporation Divisions February 20, 1986 CAW-86-017 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Corrrnission Washington, D.C. 20555
Subject:
RdF RTD Installation Safety Evaluation for D. C. Cook Unit 2, WCAPS 11080 and 11081.
Reference:
American Electric Power Service Corporation Letter of February, 1986.
Dear Mr. Denton:
The p ro p rietar y material for which withholding is being requested in the reference letter by the American Electric Power Service Corporation for the D. C. Cook Plant Unit 2 is further identified in an affidavit signed by the owner of the proprietary information, Westinghouse Electric Corporation. The affidavit, which accompanies this letter, sets forth the basis on which the information may be withheld from public disclosure by the Cormrrission and addresses with spe'cificity the considerations listed in paragraph (b)(4) of 10CFR Section 2 .790 of the Commission's regulations.
The proprietary material for which withholding is being requested is of the same technical type as that proprietary material previously subnitted with Application for Withholding CAW-76-060.
Accordingly, this letter authorizes the utilization of the accompanying affidavit by American Electric'+ower Service Corporation.
Correspondence with respect, to the proprietary aspects of the application for withholding or the Westinghouse affidavit should reference this letter, CAW-86-017, and should be addressed to the undersigned.
Very truly yours, Bb0320030i 8b03i4 Sent,MC C Mg&gCCC LC<D Rober t A. iesemann, Manager LVT/dmr Regulatory 8 Legislative Affairs Enclosure(s) cc: E. C. Shomaker, Esq.
Office of the Executive Legal Director, NRC
PROPRZETARY INFORMATION NOTICE TRANSMITTED HEREWITH ARE PROPRIETARY AND/OR NON-PROPRIETARY VERSIONS OF DOCUtKNTS FURNISHED TO THE NRC IN CONNECTION WITH REQUESTS FOR GENERIC AtiD/OR KANT SPECIFIC REVIEM AND APPROVAL.
ZN ORDER TO CONFORM TO THE REQUIRKYMTS OF 10CFR2.790 OF THE COMYESSION'S EMULATIONS CONCERNING %E PROTECTION OF PROPRIETARY INFORMATION SO SUBMITTED TO THE NRC, THE INFORMATION WHICH IS PROPRIETARY IN THE PROPRIETARY VERSIONS IS CONTAINED WITHIN BRACKETS AND %HERE THE PROPRIETARY ZNFORNTZON HAS BEEN DE ETED.IN THE NON-PROPRIETARY VERSIONS KLY THE BRACKETS REMAIN~ THE ZNFOBMTION %AT %AS CONTAINED WITHIN THE BRACKETS ZN THE PROPRIETARY VERSIONS HNING BEEN DELETED. THE JUSTIFICATION FOR QJLIMING 'SHE INFORMATION SO DESIGNATED AS PROPRIETARY ZS INDICATED ZN BOTH VERSIONS BY MEANS OF LCMER CASE LHTERS (a) THROUGH (g) CONTAINED WITHIN PAPENTHESES LOCATED AS A SUPERSCRIPT IP~ "DZATELY FOLLCMZNG %HE BRACKETS ENCLOSING EACH ITEM OF INFORMATION BEING ZDENTIFZED AS PROPRIETARY OR ZN THE MARGIN OPPOSITE SUCH INFORMATION. 'THESE LMEB CASE LETTERS REFER TO WE TYPES OF INFORMATION WESTINGHOUSE CUSTOMARILY HOLDS IN CONFIDENCE IDENTIFIED ZN SECTIONS (4)(ii)(a) through (4)(ii)(g) OF THE AFFIDAVIT ACCOMPANYING THZS TRANSVAAL PURSUANT TO 10CFB2.790(b)(1).
AH-76-60 AFFIDAVIT CONl<0t>LJEALTH OF PEHfhSYLVANIA:
ss COUNTY OF ALLEGHEHY:
Before me, the undersigned authority, personally appeared Robert A; lliesemann, who, being by me duly sworn according to law, de-poses and says that he is authorized to execute this Affidavit on behalf of llestinghouse Electric Corporation ("Mestinghouse") and that the aver-ments of'act set forth in this Affidavit are true and correct to the best of his knowledge, information, and belief Robert A. Niesemann, tlanager Licensing Programs Sworn to and subscribed before me this ~ day
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of U'Ci:a 6SL/ '1976.
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MZl~ P 8@cCe~
Notary Publ i c
W2 0 AW-76-60 (1) I am thanager, Licensing Programs, in the Pressurized Water Reactor Systems Division, of Westinghouse Electric Corporation and as such,
.I have been specifically delegated the function of reviewing the proprietary information sought to be withheld from public dis-closure -in connection with nuclear power plant licensing or rule-making proceedings, and am authorized to apply for its withholding on behalf of the Westinghouse Water Reactor Divisions.
(2) I am making this Affidavit in conformance with the provisions of 10 CFR Section 2.790 of the Commission's regulations and in con-junction with the,Westinghouse application for withholding ac-companying this Affidavit.
(3) I have personal knowledge of the criteria and procedures utilized by Hestinghouse Nuclear Energy Systems in desi gnating information
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as a trade secret, privileged or as confidential commercial or
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financial information.
~ ~
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(4) Pursuant to the provisions of paragraph (b)(4) of Section 2.790 of the Commission's regulations, the following is furnished for consideration by the Commission in determining whether the in-formation sought to be withheld from public disclosure should be
. withheld.
(i) The information sought to be withheld'from public disclosure is owned and has been held in confidence by Westinghouse.
C
w3 AW-76-60 E
(ii) The information is of a type customarily held in confidence by Mestinghouse and not customarily disclosed to the public.
llestinghouse has a rational basis for determining the types o-information customarily held in confidence by't and, in that
. connection, utilizes a system to determine when and whether to hold certain types of information in confidence. The ap-,
plication of that system and the substance of that system constitutes 4!estinghouse policy and provides the rational basis required.
Under that system, information is held in confidence if it falls in one or more of several types', the release of which might result in the loss of an existing or potential com-petitive advantage, as follows:
(a) The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.)
where prevention of its use by any of l!estinghouse's competitors without license from Westinghouse constitutes
'a competitive economic advantage over other companies.
(b) It consists of supporting data, including test data, relative to a process (or component, structure, tool, method, etc.), the application of which data secures a competitive economic advantage, e.g., by optimization or
-- improved marketability.
All-76-60 (c) Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product.
(d) It reveals cost or price in,ormation, production cap-acities, budget levels, or commercial strategies of Westinghouse, its customers or suppliers.
(e) -R-reveals aspects of past, present, or future West-inghouse or customer funded development plans and pro-grams of potential commercial value to Westinghouse.
(f) It contains patentable ideas, for which patent pro-tection may be desirable.
(g) It is not the property of Westinghouse, but must be treated as proprietary by Westinghouse according to agreements with the owner.
There are sound policy reasons behind the Westinghouse system which include the following:
(a) The use of such information by Westinghouse gives Westinghouse a competitive advantage over its com-petitors. It is,'herefore, withheld from disclosure
.td protect the Westinghouse competitive position.
~ - 'I AH-76-60
'I (b) It is information which is marketable in many ways.
The extent to 'which such information is available to competitors diminishes the Westinghouse ability to sell products and services involving the use of the on. 'nformati (c) Use by our competitor would put l~'estinghouse at a competitive disadvantage by reducing his expenditure of resources at our expense.
(d) Each component of proprietary information pertinent to a particular competitive advantage is potentially as valuable as the total competitive advantage. If competitors acquire components of proprietary infor-mation, any one component may be the key to the entire puzzle, thereby depriving Westinghouse of a competitive advantage.
(e)
'f Unrestricted disclosure would jeopardize the position prominence of Mestinghouse in the world market, and thereby give a market advantage to the competition in those countries.
(f) The Westinghouse capacity to invest corporate assets in research and development depends upon the success in obtaining and maintaining a competitive advantage.
AM-76-60 (iii) The information is being transmitted to the Commission in confidence and, under the provisions of 10 CFR Section 2.790, it is to be received in confidence by the Commission.
(iv) The information is not available in public sources to the best of our knowledge and bel i e f .
(v) The proprietary information sought to be withheld in this sub-mittal is that which is appropriately marked in the attach-ment to Mestinghouse letter number NS-CE-1298, Eicheldinger to, Stolz, dated December 1, 1976, concerning information relating to HRC review of MCAP-8567-P and MCAP-8568 entitled, "Improved Thermal Design Procedure," definirg the sensitivity of DhB ratio to various core parameter". The letter and attachment are being submitted in response to the NRC request at the October 29, 1976 HRC/Mestinghouse meeting.
This information enables Mestinghouse to:
(a) Justify the Mestinghouse design.
(b) Assist its customers to obtain licenses.
(c) Neet warranties.
(d) Provide greater operational flexibility to customers assuring them of safe and reliable operation.
(e) Justify increased power capability or operating margin for plants while assuring safe and reliable operation.'
(f) Optimize reactor design and performance while maintaining a high level of fuel integrity.
Further, the information gained from the improved thermal design procedure is of significant commercial value as follows:
(a) Westinghouse uses the information to perform and justify analyses which are sold to customers.
(b) Westinghouse sells analysis services based upon the experience gained and the methods developed..
Public disclosure of this information concerning design pro-cedures is likely to cause substantial harm to the competitive position of Westinghouse because competitors could utilize this information to assess and justify their own designs without commensurate expense.
The parametric analyses performed and their evaluation represent
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a considerable amount of highly qualified development effort.
This work was contingent upon a design method development pro-gram which has been underway during the past two years.
Altogether,, a substantial amount of money and effort has been expended by Westinghouse which could only be duplicated by a competitor if he were to invest similar sums of money and pro-vided $ e had the appropriate talent available.
Further the deponent sayeth not.
Attachment 5 to AEP:NRC:09161 LETTER REPORT DESCRIBING SUPPLEMENTARY CALCULATIONS TO PREVIOUSLY SUBMITTED ANALYSES, FOR D.C. COOK UNIT 2 CYCLE 6 OPERATION
THIS ATTACHMENT WILL BE SUPPLIED DIRECTLY BY EXXON NUCLEAR CO. IN THEIR LETTER NO. RAC:022:86
Attachment 6 to AEP:NRC:0916I REQUEST FOR WITHHOLDING PROPRIETARY INFORMATION ASSOCIATED WITH EXXON SUPPLEMENTARY CALCULATIONS DESCRIBED IN ATTACHMENT 5
THIS ATTACHMENT WILL BE SUPPLIED DIRECTLY BY EXXON NUCLEAR CO. IN THEIR LETTER NO. RAC:022:86
to AEP:NRC:09161
SUMMARY
OF ALLOWANCES NOT ADDRESSED IN ATTACHMENT 3
Attachment 7 is provided as an aid to assist the reviewer in understanding the development of certain values cited in the Technical Specifications. The included calculations supplement information provided in XN-NF-85-64(P), XN-NF-85-64(P) Rev. 1, and WCAP 11080. Reference to is indicated in the Remarks column of Attachment 10 for those Technical Specification items which require the additional explanation so provided.
Item A of this attachment demonstrates the development of the Reactor Coolant System (RCS) Analysis Flow Value.
Item B of this attachment demonstrates the derivation of the required minimum indicated RCS Flow in ibm/hr.
Item C of this attachment demonstrates the conversion of the minimum indicated RCS flow obtained in Item B from ibm/hr to gpm.
Item Dl provides the minimum indicated pressurizer pressure indication value in psig for Mode 1 operation.
Item D2 provides the minimum indicated pressurizer pressure indication value in psig for Modes 2 & 3 operation.
ATTACHMENT 7 A. ANALYSIS VALUE OF REACTOR COOLANT SYSTEM (RCS) FLOW Nominal RCS Flow with 10% Steam Generator 6 Tube Plugging 141.3 X 10 ibm/hr 6
Flow Measurement Uncertainty (3.5%) 5.0 X 10 ibm/hr 6
Flow Measurement Repeatability 3.4 X 10 ibm/hr Analysis'low: 6 141.3 E6 - 5.0 E6 - 3.4 E6 132.9 X 10 ibm/hr B. TECHNICAL SPECIFICATION MINIMUM INDICATED REACTOR COOLANT SYSTEM (RCS)
FLOW (ibm/hr)
Nominal RCS Flow with 10% Steam Generator 6 Tube Plugging 141.3 X 10 ibm/hr 6
Flow Measurement Repeatability 3.4 X 10 ibm/hr Correction to Flow Measurement Repeatability to Support Larger Pressure Allowance 6 (Section 15.0.2, XN-NF-85-64(P) Rev. 1) 0.7 X 10 ibm/hr Modified Flow Measurement Repeatability: 6 3.4 E6 - 0.7 E6 2.7 X 10 ibm/hr Minimum Indicated RCS Flow: 6 141.3 E6 - 2.7 E6 138.6 X 10 ibm/hr C. TECHNICAL SPECIFICATION MINIMUM INDICATED REACTOR COOLANT SYSTEM (RCS)
FLOW (gpm) 6 Minimum Indicated RCS Flow 138.6 X 10 ibm/hr RCS Pressure 2250 psia T 542.3 F cold 1 Gallon 0.13368 cu.ft.
Specific Volume of Water at Stated Pressure and Temperataure Conditions (1967 ASME Steam Tables) 0.021119 ft3 /ibm RCS Flow - (13).6 E6 ibm/hr) X (1 hr/60 min)
X (0.021119 ft /ibm) X (1 gal/0.13368 ft.)
Minimum Indicated RCS Flow- 364,940 gpm Minimum Indicated RCS Flow/Loop- 91,240 gpm
'. INDICATED PRESSURIZER PRESSURE DNB LIMIT (TABLES 3.2-1 AND 3.2-2)
The method of determining the allowance for pressure readability is similar to that provided in WCAP 11080 for the indicated T values for the terms used in the calculation, with the exception ave'ctual of the rack calibration allowance and the indicator readability, were also obtained from WCAP 11080 Page viii. The value used for the rack calibration allowance was obtained from the pressurizer pressure channel calibration procedure; the value used for indicator readability was determined from a review of the indicator span and scale.
The total pressurizer pressure channel allowance was determined to be 3.41% of span which equates to 27.29 psia.
Assuming a minimum of 3 channels available for averaging, the allowance may be reduced by the square root of 3. This yields a final pressurizer pressure readability allowance of 15.8 psia.
- 1) Minimum Indicated Pressure in Mode 1 Nominal Pressure- 2250 psia Pressure Control Allowance (WCAP 11080, Page 3) Proprietary Indication Allowance- 15.8 psi Allowance assumed .in Analysis 40 psi Additional Pressure Allowance accounted for by .5% increase in" minimum RCS Flow (Section 15.0.2 XN-NF-85-64(P) Rev. 1)- 7.5 psi Analysis Pressure:
2250 7.5- 2202.5 psia Minimum Indicated Pressurizer Pressure:
2202 ' + 15.8- 2218.3 psia Table 3.2-1 Value for Minimum Indicated Pressure in Mode 1:
2220 psia 2205 psig
- 2) Minimum Indicated Pressure in Modes 2 & 3 Analysis Pressure 2175 psia Minimum Indicated Pressure:
2175 + 15.8 2190.8 psia Table 3.2-2 Value for Minimum in Modes 2 & 3:
Indicated'ressure 2191 psia 2176 psig
Attachment 8 to AEP:NRC:09161 LIST OF PREVIOUSLY SUBMITTED ANALYSES FOR D.C. COOK UNIT 2 CYCLE 6 OPERATION
ATTA ~ T 8 LIST OF PREVIOUSLY SUBMITTED ANALYSES DOCUMENTS Applicable AEP:NRC:
Item Document No. Letter No.
POWER DISTRIBUTION CONTROL PHASE 2 Technical Specification changes XN-NF-77-57 AEP:NRC:0575 to incorporate PDHII power XN-NF-77-57 Supp 1 dated: 8/24/81 distribution control technique 2 ~ Technical Specification changes XN-NF-77-57 Supp 2 AEP:NRC:0710 to include + 34 bI band dated: 7/12/82 II. D. C. COOK UNIT 2 CYCLE 5 LICENSING
- l. Inadvertent boron dilution at Donald C. Cook AEP:NRC:0860I shutdown while on RHR. Nuclear Plant dated: 5/17/84 Updated FSAR Section 14.1.5 III. D- C. COOK UNIT 2 ENC FUEL EXAMINATION
- 1. Examination of ENC Fuel XN-NF-84-69(P) AEP:NRC:0860U Irradiated at D.C. Cook Unit 2 dated: 11/21/84
ATTAC 8 LIST OF PREVIOUSLY SUBMITTED ANALYSES DOCUMENTS Continued Applicable AEP:NRC:
Item Document No. Letter No.
VS D.C. COOK UNIT 2 CYCLE 6 LICENSING Exxon Nuclear Methodology for XN-NF-84-73(P) AEP:NRC:0916B PWRs: Analyses of Chapter 15 events dated: 9/18/85 2 ~ D.C. Cook Unit 2 Limiting Break XN-NF-85-68(P) AEP:NRC 0916H LOCA/ECCS Analysis; 104 Steam dated: 10/8/85 Generator Tube Plugging and K(Z) Curve 3 ~ D.C. Cook Unit 2 Safety Analysis Report XN-NF-85-28 AEP:NRC:0916G dated: 10/18/85 4 ~ D.C. Cook Unit 2 Safety Analysis XN-NF-85-28(P) AEP:NRC: 0916G Report: Disposition of Standard 'Supplement 1 dated: 10/18/85 Review Plan Chapter 15 Events
- 5. Plant Transient Analysis for XN-NF-85-64(P) AEP NRC 0916C D.C. Cook Unit 2 with 10< Steam dated: ll/15/85 Generator Tube Plugging
- 6. Additional information requested by N/A AEP: NRC: 0916M the NRC regarding the D.C. Cook dated: 3/5/86 Unit 2 Cycle 6 reload, responses to questions 1, 2, 3, 4, 7, and 11 7 ~ Additional information requested by N/A TO BE SUBMITTED the NRC regarding the D.C. Cook Unit 2 Cycle 6 reload, responses to questions 5, 6, 8, 9, and 10
Attachment 9 to AEP:NRC:0916I PRINCIPAL CHARACTERISTICS FOR NUCLEAR ANALYSIS OF CYCLE 6 FUEL
Q.C Cook Unit 2, Principal Characteristics for Nuclear Analysis of Cycle 6 Fuel
~Re ion 6 ~Re ion 6 ~Re ion 7 Region 8 Nominal Enrichment (w/o) 3.40 3.65 3.64 3e83 Nominal Oensity (X TO) 95 94 94 94 Pellet 00 (in) 0.3225 0.3030 0.3030 0. 3030 Clad 00 (in) 0.374 0.360 0.360 0.360 Oiametral Gap (in) 0.0065 0.0070 0.0070 0.0070 Clad Thickness {in) 0.0225 0.0250 0.0250 0.0250 Rod Pitch {in) 0.496 0.496 0.496 0.496 Spacer Material Inconel Bi-Metallic Bi-Metallic B i -iiletal 1 i c Fuel Supplier ENC ENC ENC.
Fuel Stack Height Nominal {in) 144 144 144 144 Number of Assemblies 12 92 88 Regionwise Loading
{ MTU) 0.458 4.822 36.906 35.300 Exposure {MWd/MTU)
BOC6 24,713 27,690 19,421 0 EOC6 39,453 37,791 36,449 19,633 Incremental 14,740 10,101 17,028 19,633
Attachment 10 to AEP:NRC:09161
SUMMARY
OF D.C. COOK UNIT 2 CYCLE 6 PROPOSED TECHNICAL SPECIFICATION CHANGES
AEP:NRC:09 ATTACHMENT 10 UMMARY DESCRIPTIONS FOR D. C. COOK UNIT CYCLE 6 PROPOSED TECHNICAL SPECIFICATION PAGE PAGE SECTION DESCRIPTION REMARKS I AgIIIg INDEX 001 Modifications to Index, corres- Editorial change.
IV,X ponding to changes in the body of Technical Specifications.
1-8 Definition 002 Definition of APL is added. Editorial change; definition included 1.38 for clarity.
2-1 F 1.1 003 Removed r'eference to Figure Three loop operation in Modes 1 and 2
-2.1-2 and three loop operation. will be prohibited.
2-2 Figure 2.1-1 004 Revised reactor core safety New limits are based on analysis for limits. 10% steam generator tube plugging. See Figure 15.0.7-2 of XN-NF-85-64(P).
005 Removed reference to Power Editorial change to achieve greater Range Neutron Flux Trip and consistency between units.
associated dashed line on graph.
006 Added table of figure break- Editorial change to provide more points. precise information.
2-3 Figure 2.1-2 007 Figure is removed. Three loop operation in Modes 1 and 2 will be prohibited.
NOTE: Pound sign (4) is reference number to each change referred to in Attachment 1.
AEP:NRC:0 ATTACHMENT 10 UMMARY DESCRIPTIONS FOR D. C. COOK UNI CYCLE 6 PROPOSED TECHNICAL SPECIFICATION PAGE PAGE SECTION DESCRIPTION REMARKS 2-5 Table 2.2-1 008 The allowable value for This value is revised to reflect the Overpower AT is directed to value used in the analysis for 10%
Note 4. steam generator tube plugging and revisions to allowances to permit oper-ation with RdF RTDs. See Table 15.0.7-3 of XN-NF-85-64(P) and Attachment 3.
009 Allowable value for loss of Change to 'provide greater flow trip changed. consistency between units. New value more conservative than current value and is supported by Attachment 3.
010 Design flow value in footnote This value is changed to reflect the is changed. value used in the analysis for 104 steam generator tube plugging and revisions to allowances to permit operation with RdF RTDs. See Table 15.0.2-1 of XN-NF-85-64(P). An increase in required flow to accomodate a pressure readability allowance is described in Attachment 5. The relat-ionship between analysis flow and Technical Specification flow is dis-cussed in Attachment 7.
2-6 Table 2.2-1 Oll Allowable value for steam Changed to value resulting from new generator low-low level trip analysis of trip allowances performed changed. by Westinghouse. See Attachment 3.
2-7 Table 2.2-1 012 "t" is replaced by "~" in the Editorial change; to achieve greater (Note 1) equation. consistency with STS, Rev. 4 and Unit 1 Technical Specifications.
013 T's changed to < 574.1 F.
1 This value is revised to reflect the value used in the analysis for 10%
steam generator tube plugging. See Table 15.0.7-2 of XN-NF-85-64(P).
AEP:NRC:09 ATTACHMENT 10 UMMARY DESCRIPTIONS FOR D. C. COOK UNI CYCLE 6 PROPOSED TECHNICAL SPECIFICATION PAGE PAGE SECTION DESCRIPTION REMARKS 3/4 1-3 3. 1. 1. 2 023 Revised to include MODE 4 and A new analysis of the dilution accident 4.1.1.2 MODE 5 in the same specific- for MODES 4 and 5 was performed. See ation. Revised Technical section 15.4.6.3.1 of XN-NF-85-64(P)
Specification requirements and Attachment 5.
based on new dilution accident analysis in MODES 4 and 5.
3/4 1-3a; 3.1.1.2 024 Pages added due to length of Editorial change.
3/4 1-3b 4 '.1.2 new specification.
3/4 1-4 3.1.1.3 025 Footnote added. The Technical Specification boron conc-entration in the RWST is sufficient to provide adequate shutdown margin from expected operating conditions.
3/4 1-11 3.1.2.3.a 026 Footnote added. The Technical Specification boron conc-entration in the RWST is sufficient to provide adequate shutdown margain from expected operating conditions.
3/4 1-13 F 1.2.5 027 Footnote added. The Technical Specification boron conc-entration in the RWST is Sufficient to provide adequate shutdown margain from expected operating conditions.
3/4 1-15 3.1.2.7 028 Changed minimum RWST volume. A new analysis of dilution accident for MODE 5 was performed. See Attachment 5 ~
3/4 1-23 3.1.3.4 029 ACTION statement b removed. Three loop opqeation in Modes 1 and 2 will be prohibited.
3/4 1-25 3.1.3.6 030 Reference to Figure 3.1-2 is Three loop operation in Modes 1 and 2 removed. will be prohibited.
3/4 1-27 Figure 3.1-2 031 Figure is removed. Three loop operation in Modes 1 and 2 will be prohibited.
AEP NRC 0 ATTACHMENT 10 UMMARY DESCRIPTIONS FOR'D. C. COOK UNI CYCLE 6 PROPOSED TECHNICAL SPECIFICATION PAGE PAGE SECTION DESCRIPTION REMARKS 2-8 Table 2.2-1 014 The values of Kl, K2, and K3 These values are revised to reflect the (Note 1) are changed. values in the analysis for 104 steam generator tube plugging and revisions to allowances to permit operation with RdF RTDs. See Table 15.0.7-2 of XN-NF-85-64(P) and Attachment 3.
015 The definition of f (hI) is Most conservative values based upon changed: -40 percent. is changed Tables 15.0.7-2 and 15.0.7-3 of to -31 percent and 1.8 percent XN-NF-85-64 (P) . The OPL T and OTb T is changed to 2.9 percent. share one f(hI) module.
016 Parameters for three loop Three loop operation in Modes 1 and 2 operation are removed. will be prohibited.
2-9 Table 2.2-1 017 T" is changed to < 574.1 F. This value is revised to reflect the (Notes 2,3,4) value used in the analysis for 10%
steam generator tube plugging. See Table 15.0.7-3 of XN-NF-85-64(P).
018 The definition of revised.
f (hI) is Most conservative values based upon Tables 15.0.7-2 and 15.0.7-3 of XN-NF-85-64(P). The OPLT and OTBT share one f (b I) module.
019 Note 3 is revised and Note 4 Revisions to allowable values to permit is added. operation with RdF RTDs. See Attachment 3.
~4 3/4 1-1 3.1.1.1 020 APPLICABILITY changed to MODES Editorial cha~e to move MODE 4 SHUT-1, 2, and 3. DOWN MARGIN Specification to Specification 3.1.1.2.
3/4 1-2 4 ~ 1. 1. 1. 1 021 Surveillance changed to MODE 3 Editorial change to move MODE 4 SHUT-only. DOWN MARGIN Surveillance to Surveill-ance 4.1.1.2.b.
4 1.1.1.2 022 Add shutdown margin surveillance. This surveillance required in Section 15.1.3.4 of XN-NF-85-28(P), Supp. l.
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4 '.1.1.3
AEP NRC ATTACHMENT 10 UMMARY DESCRIPTIONS FOR D. C. COOK UN CYCLE 6 PROPOSED TECHNICAL SPECIFICATIO PAGE PAGE SECTION DESCRIPTION 3/4 2-2 3.2.l.a.2.c 032 Exemption from AFD requirements The Axial Power Distribution Monitoring for APDMS calibration is removed. System (APDMS) is not used. The plant will operate below the Allowable Power Level (APL) .
3/4 2-3 4 2~1 3 033 F M (Z) is changed to APL. The combined F (Z) target flux 4.2 '.4 R8ferenced specification surveillance c8anged to combined APL-target flux surveillance. See number has changed.
Technical Specification 3.2.6.
3/4 2-5 3.2.2 034 The F limit values of 2.04 and This reflects new F limits from 4.08 8re changed to 2.10 and XN-NF-85-68(P):"Donald C. Cook Unit 2 4.20 respectively for Exxon Limiting Break LOCA/ECCS Analysis, 10%
Nuclear Co. fuel. Stean Generator Tube Plugging, and K(Z)
Curve." The new analysis used reflood correlations based on FCTF data. See Table 2.2 of XN-NF-85-68(P).
035 Description of F (Z) penalties Editorial change for clarity.
moved from surveillance to LCO.
036 "where" removed from definition Editorial change for clarity.
"and" removed from definition of K(Z) .
037 Modified ACTION existing state- In the current Technical Specification ment a.l to remove the require- 3.2.2, ACTION a.l requires that the ment to lower the Overpower bT OPAT trip setpoint reduction be per-(OPAT) in hot standby. formed whenthe reactor is in hot standby. Thjp has been deleted. The change in the ACTION- statement for specification 3.2.2 is consistent with the draft version of the Westinghouse Standardized Technical Specifications, Revision 5. Our evaluation indicated that the reduction of the Overpower hT setpoint can be done while the reactor is in Mode l.
3-2 ' ' 038 ACTION 3.2.2.a.2 -is removed. The APDMS is not used. The plant will operate below APL.
AEP:NRC:0 ATTACHMENT 10 Y DESCRIPTIONS FOR D. C. COOK UNI CYCLE 6 PROPOSED TECHNICAL SPECIFICATION PAGE PAGE SECTION DESCRIPTION REMARKS 3/4 2-6s 4 '.2.2 039 Much of this surveillance Specification is simplified. The PDC-II requirements that were in this 3/4 2-7 requirement has been moved to APL Specification 3.2.6. specification are now incorporated in specification 3.2.6. No provisions of current Technical Specifications other than those pertaining to APDMS and the modification to existing ACTION statement a.l are described in XN-NF-77-57; XN-NF-77-57, Supplement 1; and XN-NF-77-57, Supplement 2, "Exxon Nuclear Power Distribution Control for Pressurized Water Reactors, Phase 2".
3/4 2-8(a) Figure 3.2.2(a) 040 The figure is renormalized to This reflects new F limits from 2.10 from 2.04 for Exxon Nuclear XN-NF-85-68(P):"DonRld C. Cook Unit 2 Co. fuel. Limiting Break LOCA/ECCS Analysis, 10%
Steam Generator Tube Plugging, and K(Z) Curve." The new analysis used reflood correlations based on FCTF data. See Figure 2.1 of XN-NF-85-68(P).
3/4 3/4 2-9 2-10; 3 '.3 4.2.3.1 041 These Technical Specifications are converted to Unit 1 Flow rate and F are separated in the Technical SpeciBcations to achieve 3/4 2-11; Figure 3.2-4 Technical Specification format. greater consistency between units.
3/4 2-12 Figure 3.2-5 The trade-off between flow and F> is eliminated. Flow limit moved fry Specification 3.2.3 to 3.2.5.1. See Tables 15.0.3-1 of XN-NF-85-64(P) and 3.5 of XN-NF-Q-68(P) for F hH
SUMMARY
DESCRIPTIONS FOR D. C.
AEP:NRC: I ATTACHMENT 10 COOK UNIT 2 CYCLE 6 PROPOSED TECHNICAL SPECIFICATIONS PAGE PAGE SECTION DESCRIPTION REMARKS 3/4 2-15 3.2.5 ' 042 Reactor Coolant System Total Flow rate and F are separated in the Flow Rate is added as a DNB Technical SpeciHcations to achieve limit. greater consistency between units.
The trade-off between flow and F< is eliminated. Flow limit moved fry Specification 3.2.3 to 3.2.5.1. See Table 15.0.2-1 of XN-NF-85-64(P).
An increase in required flow to accom-odate a pressure readability allowance is described in Attachment 5. Justif-ications for the conservatism in the flow allowance and use of RdF RTDs is contained in Attachment 3. The relationship between analysis flow and Technical Specification flow is discussed in Attachment 7.
4 '.5 '.2 4.2.5
'.3 043 These surveillance require-ments are added for the RCS Flow surveillance requirements are taken from the old F> Technical Spec-Total Flow Rate. Converted ification. Clarificalions are added to the Unit 1 Technical to the surveillance requirements.
Specification format.
4~2~5 ~ 1.4 044 4.0.4 exemption Primary flow instrumentation is is added for flow calibrated at or near full power.
specifications.
'.5.1 045 Specifications 3.2.5 and Editorial change; this reflects the 3
4 4
' gal.1
'.5 '.2 4.2.5 have become 3.2.5.1 and 4.2.5.1.1, respectively.
addition of" a new DNB specification 3.2.5.2 and the addition of surveill-4 ' '.1.3 Specification 3.2.5.1 is ance requirements for 3.2.5.1.
4 ' '.1 ~ 4 retitled.
AEP:NRC: I ATTACHMENT 10
SUMMARY
DESCRIPTIONS FOR D. C. COOK UN 2 CYCLE 6 PROPOSED TECHNICAL SPECIFICATIO S PAGE PAGE SECTION DESCRIPTION REMARKS 3/4 2-16 Table 3.2-1 046 The parameters and footnotes Three-loop operation in Modes 1 and 2 for three loop operation are will be prohibited.
removed.
047 The value of RCS T avg is New limit based on analysis for 104 changed. steam generator tube plugging and revisions to allowances to permit operation with RdF RTDs. See Tables 15.0.2-1 and 15.0.4-1 of XN-NF-85-64(P) and Attachment 3.
048 RCS Total Flow Rate is added Flow rate and F are separated in the as a limit. Made more Technical Speci8caticns. The trade-consistent with the Unit 1 off between flow and F<H is elimin-Technical Specifications. ated. See Table 15.0.2-1 of XN-NF-85-64(P). An increase in required flow to accomodate a pressure readability allowance is described in Attachment 5. Justifications for the conservatism in the flow allowance and use of RdF RTDs is contained in Attachment 3. The relationship between analysis flow and Technical Specification flow is discussed in Attachment 7.
049 Allowance for readability An increase in required flow to accom-included for pressure limit. odate a pressure readability allowance Technical Specification value is de'scribed in Attachment 5. Calcul-remains the same. Analysis ation of thd'allowance for instrument value reduced by the value of error is discussed in Attachment 7.
the allowance. The allowance was calculated consistently with footnote *~.
050 Table is rotated on the page. Editorial change for clarity.
AEP:NRC: I ATTACHMENT 10
SUMMARY
DESCRIPTIONS FOR D. C. COOK UN 2 CYCLE 6 PROPOSED TECHNICAL SPECIFICATIO PAGE PAGE SECTION DESCRIPTION REMARKS 3/4 2-17 3.2.5 ' 051 Specification added. The limits on pressurizer pressure and 4.2.5.2 T in Mode 2 or Mode 3 (with the r8ZStor trip breakers closed and the 3/4 2-18 Table 3.2-2 052 Table added. control rod drive mechanism capable of rod withdrawal) provide protection against DNB resulting from an uncont-rolled rod withdrawal accident from a subcritical condition. They are consistent with the assumptions given in Section 15.4.1 of XN-NF-85-64(P).
When the reactor is critical, the limits of the remaining DNB analyses are conservatively applied. The instrument reading error is discussed in Attachment 7.
AEP:NRC: I ATTACHMENT 10
SUMMARY
DESCRIPTIONS FOR D C. COOK UNzT 2 CYCLE 6 PROPOSED TECHNICAL SPECIFICATIO PAGE 10 PAGE SECTION DESCRIPTION REMARKS I 3/4 2-19; 3.2.6 053 This entire Technical The APDMS, an option in current Tech-3/4 2-20 Specification is changed to nical Specifications, is not used. The an Allowable Power Level (APL) plant will operate below APL. This Technical Specification. specification is added to satisfy the requirements of the PDC-II 'power distribution control technique. No provisions of current Technical Specifications other than those pert-aining to APDMS and the modification to existing ACTION statement a.l of Tech-nical Specification 3.2.2 were deleted. PDC-II is described in XN-NF-77-57; XN-NF-77-57, Supp.l; and XN-NF-77-57, Supp.2, "Exxon Nuclear Power Distribution Control for Press-urized Water Reactors, Phase 2.<<
Requirements which were formerly in specification 3.2.2 have been incorporated in this specification.
In the current Technical Specification 3.2.2, ACTION a.l requires that the OPET trip setpoint reduction be per-formed when the reactor is in hot standby. This has been deleted. The change in the action statement for specification 3.2.2 is consistent with the draft version of the Westinghouse Standardized Technical Specifications, Revision 5. 9'Our evaluation indicated that the reduction of the Overpower LT setpoint can be done while the reactor is in Mode l.
054 F~ Limit value changed from This reflects new F limits from 2.04 to 2.10 for Exxon XN-NF-85-68(P):"Donald C. Cook Unit 2 Nuclear Co. fuel. Limiting Break LOCA/ECCS Analysis, 104 Steam Generator Tube Plugging, and K(Z) Curve." The new analysis used reflood correlations based on FCTF data. See Table 2.1 of XN-NF-85-68(P)-
AEP:NRC:09 ATTACHMENT 10 Y DESCRIPTIONS FOR D. C. COOK UNIT 2 CYCLE 6 PROPOSED TECHNICAL SPECIFICATIONS PAGE 11 PAGE SECTION DESCRIPTION REMARKS 3/4 3-2 Table 3.3-1 055 Power Range, Neutron Flux The Plant Transient Analysis requires Item 2 Functional Unit has an added the Power Range, Neutron Flux Funct-applicable mode:*. ional Unit to be operable with the reactor trip breakers in the closed position and the control rod drive mechanism capable of rod withdrawal.
This is consistent with section 15.4.1.3 of XN-NF-85-28(P), Supp. 1.
Items 7 and 8 056 References to three loop Three loop operation in Modes 1 and 2 operation are removed. will be prohibited.
057 Changed ACTION for To achieve greater consistency with functional units. STS, Rev. 4 and Unit 1 Technical Specifications.
3/4 3-4 Table 3.3-1 058 Reactor Coolant Pump Breaker To achieve greater consistency with Item 20B Position Trip Above P-7 has STS, Revision 4.
an added exemption from 3.0.4 applicability.
3/4 3-5 Table 3.3-1 059 Footnote ** is removed. Three loop operation in Modes 1 and 2 Notation will be prohibited.
AEP:NRC:0 ATTACHMENT 10 UMMARY DESCRIPTIONS FOR D. C. COOK UNIT 2 CYCLE 6 PROPOSED TECHNICAL SPECIFICATIONS PAGE 12 PAGE SECTION DESCRIPTION 3/4 3-7 Table 3.3-1 060 Action 8 is removed. Editorial change; Action 8 is not used.
061 Action 9 is removed. Three loop operation in Modes 1 and 2 will be prohibited.
3/4 3-8 Table 3.3-1 062 Converted Turbine Pressure Editorial change.
setpoint portion of P-7 from 66 psia to 51 psig.
3/4 3-9 Table 3.3-2 063 Response time is added Analysis- value from Table 15.0.7-1 of for Pressurizer Pressure XN-NF-85-64(P). Conservative Technical High Functional Unit. Specification value chosen to achieve greater consistency with Unit 1 Technical Specifications.
3/4 3-11 Table 4.3-1 064 Power, Range, Neutron Flux The Plant Transient Analysis requires Functional Unit has an the Power Range, Neutron Flux Funct-additional Channel Function ional Unit to be operable .with the Test (S/U(1)) and an additional reactor trip system breakers in the mode in which surveillances are closed position and the control rod required:*. drive mechanism capable of rod with-drawal. See section 15.4.1.3 of XN-NF-85-28(P), Supplement 1.
065 Power, Intermediate, and Source Exemptions are provided for surveill-Range Neutron Flux and Loss of ances which must be performed in the Flow Single Loop Functional applicable mode.
Units have added exemptions ~ I from Specification 4.0.4. Over-power AT and Overtemperature hT Functional Units have added exemptions from Specification and f2 (~I) penalties.
AEP:NRC!0 ATTACHMENT 10 UMMARY DESCRIPTIONS FOR D. C. COOK UNIT CYCLE 6 PROPOSED TECHNICAL SPECIFICATION PAGE 13 PAGE SECTION DESCRIPTION REMARKS 3/4 3-13 Table 4.3-1 066 Footnotes (8) and (9) are added. See remarks for 3/4 3-11 above.
Notation 3/4 3-15; Table 3.3-3 067 References to three loop Three loop operation in Modes 1 and 2 3/4 3-16; operation in Modes 1 and 2 will be prohibited.
3/4 3-17 are removed.
3/4 3-18 3/4 3-19; 068 Reference to ggg footnote for The Differential Pressure Between 3/4 3-20 Differential Pressure Between Steam Lines-High actuation differs Steam Lines-High Functional from other ESF Actuation signals in Unit changed to gggg footnote. that a signal from one loop is comp-ared to signals in the other loops.
Placing all channels associated with the idle loop in trip would result in an ESF actuation. This actuation would preclude 3 loop operation..
Therefore, the appropriate channels to trip are the bistables which indicate low active steam pressure relative to the idle loop. This action reduces the ESF actuation logic for the active loop differential pressures from 2/3 to 1/2. An ESF actuation does not result because the three bistables, which indicate low idle loop steam pressure relative to the active loops, and which are in a 2/3 logic, are not tripped.
AEP:NRC:0 ATTACHMENT 10
SUMMARY
DESCRIPTIONS FOR D. C. COOK UNIT 2 CYCLE 6 PROPOSED TECHNICAL SPECIFICATIONS PAGE 14 PAGE SECTION DESCRIPTION REMARKS 3/4 3-15; Table 3.3-3 069 References to the 1982 Editorial change; the 1982 refueling 3/4 3-16; (Cont'd) refueling outage are outage has already occured.
3/4 removed.
3-18; 3-17'/4 3/4 3-19; 070 Steam Generator Water Level Section 15.1.2.3 of the Disposition of 3/4 3-20 High-High Functional Unit has an Events, XN-NF-85-28(P), Supplement 1, (Cont'd) added applicable mode: requires the Steam Generator Water Level High-High Functional Unit to be operable when operating with the main feedpumps feeding the steam generators in Modes 3 and 4. The availability of feedwater isolation on high-high steam generator level limits the volume of cold water that can be added to the steam generators in any feedwater malfunction. This limits reactivity addition to the core.
3/4 3-21 Table 3.3-3 071 Footnote gggg is added. See remarks for footnote gggg for Notation pages 3/4 3-15 through 3/4 3-20.
072 Footnote $ is added. Section 14.1.2.3 of the Disposition of Events, XN-NF-85-28(P), Supplement 1, requires the Steam Generator Water Level High-High Functional Unit to be operable when operating on the low flow feedwater preheating system.
Footnotes 073 Conditions for blocking These conditihns are required in sect-g and gg safeguards actuations ion 15.1.3.4 of XN-NF-85-28(P), Supp.l.
are added.
AEP:NRC 0916I ATTACHMENT 10
SUMMARY
DESCRIPTIONS FOR D. C. COOK UNIT 2 CYCLE 6 PROPOSED TECHNICAL SPECIFICATIONS PAGE 15
, PAGE SECTION DESCRIPTION REMARKS 3/4 3-2la Table 3.3-3 074 ACTION statements moved, from Editorial change; expanded table ACTION previous page to this new notation necessitates additional page.
statements page.
3/4 3-22 Table 3.3-3 075 Reworded Condition and Set- This change clarifies the definitions point, Function description of the interlock and makes the defin-for P-12 interlock. ition less ambiguous. Patterned after STS, Rev.4.
076 Setpoint limit values are New limits are based on revisions to revised. allowances to permit operation with RdF RTDs. See Attachment 3.
077 P-12 function description Editorial change; safety injection revised to remove reference actuation occurs on low steam line to high steam line flow. pressure only. There has never been a coincidence with high steam flow on-Unit 2.
AEP NRC:09 ATTACHMENT 10 UMMARY DESCRIPTIONS FOR D. C. COOK UNIT 2 CYCLE 6 PROPOSED TECHNICAL SPECIFICATIONS PAGE 16 PAGE DESCRIPTION REMARKS 3/4 3-25 Table 4.3-2 078 Allowable value of low-low Changed allowable value to be consist-T changed. ent with Unit 1. This change is supp-orted by analysis performed by Westinghouse to permit operation with RdF RTDs. The Technical Specification value is more conservative than the analysis value. See Attachment 3.
3/4 3-25a Table 4.3-2 079 Allowable values for auxiliary Changed to value resulting from new feedpump actuations on low-low analysis of trip allowances performed steam generator level changed. by Westinghouse. See Attachment 3.
3/4 3-32 Table 4.3-2 080 Steam Generator Water Level Section 14.1.2.3 of the Disposition of High-High Functional Unit has Events, XN-NF-85-28(P), Supplement, 1, an additional required mode: $ . requires the Steam Generator Water Level High-High Functional Unit to be operable when operating with the main feedpumps feeding the steam generators in Modes 3 and 4.
081 Loss of Main Feedwater Pumps Editorial change; Mode 3 applicability Mode 3 Surveillance Requirement for Loss of Main Feedwater Pumps deleted. was deleted from Table 3.3-3 in Unit 2 License Amendment 477.
3/4 3-33 Table 4.3-2 082 Footnote $ added for Steam See remark for p 3/4 3-32 above.
Generator Water Level High-High Functional Unit.
~ I 083 References to the 1982 refuel- The 1982 refuel.ing outage has already ing outage are removed. occured.
3/4 3-38 3.3.3.2 084 The references to F xy are Editorial change; F is not used for 4.3.3.2.c removed. core monitoring witPPDC-II.
3/4 3-48; 3.3.3.7 085-This entire Technical The APDMS is not used. The plant will 3/4 3-49 4.3.3.7 Specification is removed. operate below APL.
AEP NRC:0 ATTACHMENT 10 UMMARY DESCRIPTIONS FOR D. C. COOK UNIT 2 CYCLE 6 PROPOSED TECHNICAL SPECIFICATIONS
'PAGE 17 PAGE DESCRIPTION REMARKS 3/4 4-2 3.4.1.2.b 086 Criteria for the operability of The Plant Transient Analysis requries 3.4.1.2.c reactor coolant loops are estab- these changes based on the uncontrolled lished based on the status of control rod bank withdrawal from the reactor trip system breakers subcritical. See section 15.4.1.1 and/or the control rod system. of XN-NF-85-64(P).
pageos
- is added to ACTION b; 3.4.1.2 087 The Technical Specification boron ACTION b footnote added at bottom of concentration in the RWST is suff-Footnote ** icient to provide adequate shutdown margin from expected operating conditions.
3/4 4-2a 4.4 1.2.1
~ 088 Surveillances moved from Editorial change; additional text 4 4
~ ~ 1.2.2 previous page. requires moving this material.
3/4 4-3 3.4.1.3 089 ****is added to ACTION b; The Technical Specification boron 3/4 4-3a ACTION b footnote ****is added on concentration in the RWST is suff-Footnote *** p 3/4 4-3a. icient to provide adequate shutdown margin from expected operating conditions.
090 ACTION statements moved from. Editorial change; additional footnote page 3/4 4-3 to page 3/4 4-3a. requires moving this material.
AEP:NRC:09 ATTACHMENT 10
SUMMARY
DESCRIPTIONS FOR D. C. COOK UNIT 2 CYCLE 6 PROPOSED TECHNICAL SPECIFICATIONS PAGE 18 PAGE SECTION DESCRIPTION REMARKS 3/4 4-3bi 3~4 ~ 1.4 091 The entire Technical ACTION statements of Technical Spec-3/4 4-3c; 4.4.1.4 Specification is removed. ification 3.4.1.4 are currently 3/4 4-3d addressed elsewhere in Technical Spec-ifications or not needed as follows:
Below P-7:
- a. - 3 4 1.1
~ ~
- b. 3.4.1.2 and 3.4.1.3
- c. - Not needed. Since Mode 3 above P-12 is the only operation permitted for three loop operation which requires changes to safeguards or protection equipment, no mode changes dependent on ACTION statement will occur.
3/4 4-4 3.4.2 092 Additional ACTION statement Section 15.5.1 4 of the Disposition of is added. Events, XN-NF-85-28(P), Supplement 1, requires this action to prevent overpressurization due to an inadvertent increase in the RCS inventory.
093 Page 3/4 4-4 is submitted as This eliminates the need to submit a back page to a blank blank pages for pages 3/4 4-3c and 3/4 4-3b. 3/4 4-3d.-
AEP:NRC: 0 ATTACHMENT 10 UMMARY DESCRIPTIONS FOR D. C. COOK UNIT CYCLE 6 PROPOSED TECHNICAL SPECIFICATION PAGE 19 PAGE SECTION DESCRIPTION REMARKS 3/4 4-32 3.4.11 094 "operator" changed to Editorial change; to use proper termin-
"operated" ology.
095 ACTION changed to only allow NRC staff comments at December 13, one PORV or block valve inoper- 1984, meeting; the proposed changes are able. Making more than one PORV intended to ensure that the PORVs are inoperable without shutting down available to assist in RCS depressur-the reactor is not allowed. ization following a steam generator tube rupture without offsite power.
096 References to Section 6.9.1.9 To achieve greater consistency with are deleted. STS, Rev.4 and draft STS, Rev.5.
3/4 4-33 4. 4. 11. 1 097 Portions of expanded ACTION Editorial change; surveillance statement and surveillance requirement moved from previous page to requirements moved to this page.
p 3/4 4-33.
4.4.11.3 098 References to surveillances in Editorial change; the current refer-other sections changed. ences are incorrect.
AEP:NRC ATTACHMENT 10
SUMMARY
DESCRIPTIONS FOR D. C. COOK UNIT 2 CYCLE 6 PROPOSED TECHNICAL SPECIFICATIO PAGE 20 PAGE SECTION DESCRIPTION 3/4 7-1 3.7.1.1 099 ACTION b is modified to remove Three loop operation in Modes 1 and 2 three loop operation in Modes 1 will be prohibited.
and 2.
3/4 7-3 Table 3.7-2 100 Table is removed. Three loop operation in Modes 1 and 2 will be prohibited.
3/4 7-5 4.7.1.2 101 Discharge pressures for aux- The value for pump discharge pressure iliary feedwater pump flow is adecpxate to assure that in the event testing changed. of a feedwater line break, at least 600 gpm will be delivered to the intact steam generators. See section 15.2.8.3 of XN-NF-85-64(P) .
AEP:NRC:09 ATTACHMENT 10 UMMARY DESCRIPTIONS FOR D. C. COOK UNIT CYCLE 6 PROPOSED TECHNICAL SPECIFICATION PAGE 21 PAGE SECTION DESCRIPTION REMARKS 3/4 7-10 3.7.1.5 102 ACTION statements are revised. The provision of the ACTION statement for MODE 1 permitting operation in. MODE 1 with a steam generator stop valve closed is deleted. Failure to restore the stop valve to operable status in MODE 1 results in MODE 2 instead of MODE 4 operation. The reference in the MODE 2, 3 ACTION statement to continued operation in MODE 1 is deleted. The terminology is consistently changed to Cook Plant terminology. The proposed Technical Specification achieves substantially greater consistency with STS, Rev.4.
4.7.1.5 103 Exemption from Specification Exemptions are provided for surveill-4.0.4 is added for entry ances which must be performed in the into Mode 3. applicable mode.
3/4 9-8 3 ' '.1 104 Footnote
- is added. The Technical Specification boron concentration in the EST is sufficient to provide adequate shutdown margin from exepected operating conditions.
3/4 10-2 4.10 ' ' 105 Referenced specifications are Editorial change; reflects simplifica-renumbered. tion of F and APL specifications, 3.2.2 and 3.2.6 respectively. See page 3/4 2-6.
AEP:NRC:09 ATTACHMENT 10 UMMARY DESCRIPTIONS FOR'. C. COOK UNIT CYCLE 6 PROPOSED TECHNICAL SPECIFICATIONS PAGE 22 PAGE SECTION DESCRIPTION REMARKS B 2-1 2.1.1 106 References to Figure 2.1-2 Three loop operation in Modes 1 and 2 (Bases) are removed. will be prohibited.
B 2-4 2~2~1 107 Revision made to the basis of Reference was made to the "Interim (Bases) negative rate trip. Criteria for Single Dropped Rod" which was assumed in the analysis.: See section 15.4.3.4 of XN-NF-85-28(P).
B 2-5 Overtemperature 108 Paragraph referring to Three loop operation in Modes 1 and 2 hT (Bases) three loop operation is removed. will be prohibited.
2.2.1 109 Corrected spelling of the word Editorial change.
(Bases) "operation".
110 Added reference to f (~I) Cycle 6 analysis requires f(b,I) penalty penalty for OPzT. for OPDT trip. See Table 15.0.7-3 of XN-NF-85-64(P).
ill Added reference the pressurizer to the use of pressure high This function was used in the Cycle analysis. See section 15.2.1.3 of 6
trip in the loss of load event. XN-NF-85-64(P) ~
B 2-5 2.2.1 112 Moved text from page B 2-6 to Editorial change.
B 2-6 (Bases) B 2-5.
B 2-6 Loss of Flow 113 The value of P-8 is changed Editorial change.
(Bases) to 314.
114 Design flow is defined and used Revision describes Exxon DNB instead of nominal flow. methodology.
115 References to three loop loop operation in Modes and P'hree 1 2 operation are removed. will be prohibited.
B 2-6 2~2~1 =116 Moved text from page B 2-7 to Editorial. change.
B 2-7 (Bases) B 2-6.
AEP:NRC:09 ATTACHMENT 10 Y DESCRIPTIONS FOR D. C. COOK UNIT CYCLE 6 PROPOSED TECHNICAL SPECIFICATIONS PAGE 23 PAGE SECTION DESCRIPTION REMARKS B 3/4 l-l Shutdown 117 Revision to Shutdown Margin Describes Exxon analyses of steam dump Margin (Bases) Basis. failure and Mode 5 dilution transient.
Editorial clarifications made.
See section 15.1.3.4 of XN-NF-85-28(P),
Supp.l and 15.4.6.3.1 of XN-NF-85-64(P).
B 3/4 1-1; 3/4.1.1.4 118 Moved text from B 3/4 l-l to Editorial change.
B 3/4 1-2 (Bases) B 3/4 1-2.
B 3/4 1-2 Moderator 119 Revision to Moderator Temper- Revised material describes Exxon MTC Temperature ature Coefficient (MTC) basis. methodology.
Coefficient-(Bases)
Minimum 120 Revised discussion of inter- Bases were revised to more accurately Temp. for action between minimum reflect the operation of P-12 reset Criticality temperature for point.
(Bases) criticality requirement and P-12 reset point.
B 3/4 1-3 3/4.1.2 121 Revisions were made to desc-(Bases) ription of the RWST as a boration source.
AEPeNRC'09 ATTACHMENT 10 UMMARY DESCRIPTIONS FOR D. C. COOK UNIT CYCLE 6 PROPOSED TECHNICAL SPECIFICATIONS PAGE 24 PAGE SECTION DESCRIPTION REMARKS B 3/4 2-1 Power Distrib- 122 The F limit value of 2.04 This reflects new F limits from ution Limits is chRnged to 2.10 for XN-NF-85-68(P):"Donald C. Cook Unit 2 (Bases) Exxon Nuclear Co. fuel. Limiting Break LOCA/ECCS Analysis, 104 Steam Generator Tube Plugging, and 123 Tube plugging percentages K(Z) Curve." The new analysis used are changed. reflood correlations based on FCTF data. See Table 2.2 of XN-NF-85-68(P) 124 Cycle 5 margin reference Future use of Westinghouse fuel deleted. expected to be minimal.
125 Comma added. Editorial change; grammatical error.
126 "increase" changed to Editorial change; typographical error.
"increased" Axial Flux 127 The F limit value of 2.04 This reflects new F limits from Difference is changed to 2.10 for XN-NF-85-68(P):"Donald C. Cook Unit 2 (Bases) Exxon Nuclear Co. fuel. Limiting Break LOCA/ECCS Analysis, 104 Steam Generator Tube Plugging, and K(Z)
Curve." The new analysis used reflood correlations based on FCTF data. See Table 2.1 of XN-NF-85-68(P).
B 3/4 2-4 3/4.2.2 128 RCS flowrate is removed from Flow rate and F .=
are separated in the 3/4 '.3 (Bases) these specifications. NIncluding Technical SpeciHcations.
revised statement on F>H The trade-off between flow and F>H is eliminated.
measurement error. See Table 15.0.3-1 of XN-NF-85-64(B) and Table 2.1 of XN-NF-85-68(P)P 129 References to F and F> Editorial change.
expanded to include pro)need APL Technical Specification.
AEP:NRC:0 ATTACHMENT 10 UMMARY DESCRIPTIONS FOR D. C. COOK UNI CYCLE 6 PROPOSED TECHNICAL SPECIFICATIO PAGE 25 PAGE SECTION DESCRIPTION REMARKS B 3/4 2-5 3/4 ~ 2~5 130 Revisions made to basis to Editorial changes.
(Bases) distinguish between modes and refer to safety analysis.
131 RCS flowrate added to this RCS flowrate is now a DNB parameter.
specification, including discussion of surveillances.
132 Revised discussion of read- New allowance included for pressurizer ability allowances to include pressure. Flow added to DNB specific-pressurizer pressure and flow. ation. See Attachment 3 and Attachment 7.
133 "thru" becomes "through". Editorial change; typographical error correction.
134 Added paragraph describing DNB The limits on pressurizer pressure and limits for Modes 2 and 3. T in Mode 2 or Mode 3 (with the r8XStor trip breakers closed and the control rod drive mechanism capable of rod withdrawal) provide protection against DNB resulting from an uncontrolled rod withdrawal accident from a subcritical condition. They are consistent with the assumptions given in Section 15.4.1 of XN-NF-85-64(P).
3/4.2.6 135 This section is changed to an -The APDMS is not used. The plant will (Bases) Allowable Power Level (APL) -
operate below APL.
Technical Specification.
B 3/4 3-1 3/4.3.1 136 Basis material added describing Protection required for operation 3/4 ' ' main feedpump operation in with a main feedpump feeding steam (Bases) Modes 3 and 4 and the conditions generators in Modes 3 and 4 is for blocking ESF actuation. described in section 15.1.2.3 of XN-NF-85-28(P), Supp.1. Conditions for blocking safeguards actuations included in Table 3.3-3 are described in Section '15.1.3.4 of XN-NF-85-28(P).
AEP:NRC:0916I ATTACHMENT 10
SUMMARY
DESCRIPTIONS FOR D. C. COOK UNIT 2 CYCLE 6 PROPOSED TECHNICAL SPECIFICATIONS PAGE 26 PAGE SECTION DESCRIPTION REMARKS B 3/4 3-li 3/4 ~ 3 ~ 3.1 137 Basis 3/4.3.3.1. moved to Editorial change.
B 3/4 3-2 (Bases) page B 3/4 3-2.
B 3/4 3-2 3/4 ' ' ' 138 This section is removed. The APDMS is not used. The plant will (Bases) operate below APL.
B 3/4 4-1 3/4.4.1 139 References to three loop Three loop operation in Modes 1 and 2 (Bases) operation are removed. will be prohibited.
140 Additional operable loop is The Plant Transient Analysis requires required with control rods these changes based on the uncont-capable of withdrawal. rolled control rod bank withdrawal from subcritical. See section 15.4.1.1 of XN-NF-85-64(P).
B 3/4 4-la 3/4.4.2 141 All Safety Injection pumps See Section 15.5.1.4 of the 3/4.4.3 and all but one charging pump Disposition of Events, XN-NF-85-28(P), ~
(Bases) will be rendered inoperable in Supplement l.
Modes 4 and 5 if no safety valves are operable to prevent overpressurization due to an inadvertent increase in the RCS inventory.
B 3/4 4-11 3/4.4.11 3/4.4.12 142 Period converted to /. Editorial change.
(Bases)
B 3/4 7-1 3/4.7.1.1 143 References to three loop Three loop operation in Modes 1 and. 2 (Bases) operation are removed. will be prohibited.
144 Reference to Table 3.7-2 Editorial change; incorrect table is changed to Table 3.7-1. reference.
This basis is condensed to one page.
B 3/4 7-2 3/4 7.1
~ 145 Variable definitions are Editorial change; improve readability.
(Bases) moved to previous page.
~ '