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
Westinghouse Water Reactor Electric Corporation Divisions Box 355 Pittsburgh Pennsytvania 15230 0355 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S.
Nuclear Regulatory Corrrnission Washington, D.C.
20555 February 20, 1986 CAW-86-017
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 ro rietar 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.
p p
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.
Bb0320030i 8b03i4 LVT/dmr Enclosure(s)
Very truly yours, Sent,MC C Mg&gCCC LC<D Rober t A.
- iesemann, Manager Regulatory 8 Legislative Affairs 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 AFFIDAVITACCOMPANYING THZS TRANSVAAL PURSUANT TO 10CFB2.790(b)(1).
AH-76-60 AFFIDAVIT CONl<0t>LJEALTH OF PEHfhSYLVANIA:
COUNTY OF ALLEGHEHY:
ss 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
~/
of U'Ci:a6SL/ '1976.
. '7 j
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
~as a trade secret, privileged or as confidential commercial or
~
~
~
~
financial information.
(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 ifit 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
'nformati on.
(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)
Unrestricted disclosure would jeopardize the position
'f 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 ief.
(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 flexibilityto 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
~
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
Attachment 7 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 Attachment 7 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 Tube Plugging Flow Measurement Uncertainty (3.5%)
Flow Measurement Repeatability Analysis'low:
141.3 E6
- 5.0 E6
- 3.4 E6 141.3 X 10 ibm/hr 6
5.0 X 10 ibm/hr 6
3.4 X 10 ibm/hr 6
132.9 X 10 ibm/hr 6
B.
TECHNICAL SPECIFICATION MINIMUM INDICATED REACTOR COOLANT SYSTEM (RCS)
FLOW (ibm/hr)
Nominal RCS Flow with 10% Steam Generator Tube Plugging Flow Measurement Repeatability Correction to Flow Measurement Repeatability to Support Larger Pressure Allowance (Section 15.0.2, XN-NF-85-64(P) Rev.
1)
Modified Flow Measurement Repeatability:
3.4 E6
- 0.7 E6 Minimum Indicated RCS Flow:
141.3 E6
- 2.7 E6 141.3 X 10 ibm/hr 6
3.4 X 10 ibm/hr 6
0.7 X 10 ibm/hr 6
2.7 X 10 ibm/hr 6
138.6 X 10 ibm/hr 6
C.
TECHNICAL SPECIFICATION MINIMUM INDICATED REACTOR COOLANT SYSTEM (RCS)
FLOW (gpm)
Minimum Indicated RCS Flow RCS Pressure Tcold 1 Gallon Specific Volume of Water at Stated Pressure and Temperataure Conditions (1967 ASME Steam Tables)
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-Minimum Indicated RCS Flow/Loop-138.6 X 10 ibm/hr 6
2250 psia 542.3 F
0.13368 cu.ft.
0.021119 ft /ibm 3
364,940 gpm 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
ave'ctual values for the terms used in the calculation, with the exception 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)
Indication Allowance-Allowance assumed.in Analysis Proprietary 15.8 psi 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)-
Analysis Pressure:
2250
- 40
- 7.5-7.5 psi 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 Indicated'ressure in Modes 2 & 3:
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 Item POWER DISTRIBUTION CONTROL PHASE 2
Applicable Document No.
AEP:NRC:
Letter No.
2 ~
Technical Specification changes to incorporate PDHII power distribution control technique Technical Specification changes to include + 34 bI band XN-NF-77-57 AEP:NRC:0575 XN-NF-77-57 Supp 1
dated:
8/24/81 XN-NF-77-57 Supp 2
AEP:NRC:0710 dated:
7/12/82 II.
D.
C.
COOK UNIT 2 CYCLE 5 LICENSING l.
Inadvertent boron dilution at shutdown while on RHR.
Donald C.
Cook Nuclear Plant Updated FSAR Section 14.1.5 AEP:NRC:0860I dated:
5/17/84 III. D-C.
COOK UNIT 2 ENC FUEL EXAMINATION 1.
Examination of ENC Fuel Irradiated at D.C.
Cook Unit 2 XN-NF-84-69(P)
AEP:NRC:0860U dated:
11/21/84
ATTAC 8
LIST OF PREVIOUSLY SUBMITTED ANALYSES DOCUMENTS Continued Item VS D.C.
COOK UNIT 2 CYCLE 6 LICENSING Applicable Document No.
AEP:NRC:
Letter No.
2 ~
Exxon Nuclear Methodology for PWRs: Analyses of Chapter 15 events D.C.
Cook Unit 2 Limiting Break LOCA/ECCS Analysis; 104 Steam Generator Tube Plugging and K(Z) Curve XN-NF-84-73(P)
XN-NF-85-68(P)
AEP:NRC:0916B dated:
9/18/85 AEP:NRC 0916H dated:
10/8/85 3 ~
D.C.
Cook Unit 2 Safety Analysis Report XN-NF-85-28 AEP:NRC:0916G dated:
10/18/85 4 ~
5.
6.
7 ~
D.C.
Cook Unit 2 Safety Analysis Report: Disposition of Standard Review Plan Chapter 15 Events Plant Transient Analysis for D.C.
Cook Unit 2 with 10< Steam Generator Tube Plugging Additional information requested by the NRC regarding the D.C.
Cook Unit 2 Cycle 6 reload, responses to questions 1, 2, 3, 4, 7, and 11 Additional information requested by the NRC regarding the D.C.
Cook Unit 2 Cycle 6 reload, responses to questions 5,
6, 8, 9, and 10 XN-NF-85-28(P)
'Supplement 1
XN-NF-85-64(P)
N/A N/A AEP:NRC: 0916G dated:
10/18/85 AEP NRC 0916C dated: ll/15/85 AEP: NRC: 0916M dated:
3/5/86 TO BE SUBMITTED
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)
Nominal Oensity (X TO)
Pellet 00 (in)
Clad 00 (in)
Oiametral Gap (in)
Clad Thickness {in)
Rod Pitch {in)
Spacer Material 3.40 95 0.3225 0.374 0.0065 0.0225 0.496 Inconel 3.65 3.64 94 0.3030 0.360 0.0070 0.0250 0.496 94 0.3030 0.360 0.0070 0.0250 0.496 Bi-Metallic Bi-Metallic 3e83 94
- 0. 3030 0.360 0.0070 0.0250 0.496 B i -iiletal 1 ic Fuel Supplier Fuel Stack Height Nominal {in)
Number of Assemblies Regionwise Loading
{MTU)
Exposure
{MWd/MTU)
BOC6 EOC6 Incremental 144 0.458 24,713 39,453 14,740 ENC 144 12 4.822 27,690 37,791 10,101 ENC 144 92 36.906 19,421 36,449 17,028 ENC.
144 88 35.300 0
19,633 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 IV,X 001 Modifications to Index, corres-Editorial change.
ponding to changes in the body of Technical Specifications.
1-8 2-1 2-2 2-3 Definition 1.38 F 1.1 Figure 2.1-1 Figure 2.1-2 002 Definition of APL is added.
003 Removed r'eference to Figure
-2.1-2 and three loop operation.
004 Revised reactor core safety limits.
005 Removed reference to Power Range Neutron Flux Trip and associated dashed line on graph.
006 Added table of figure break-points.
007 Figure is removed.
Editorial change; definition included for clarity.
Three loop operation in Modes 1 and 2
will be prohibited.
New limits are based on analysis for 10% steam generator tube plugging.
See Figure 15.0.7-2 of XN-NF-85-64(P).
Editorial change to achieve greater consistency between units.
Editorial change to provide more precise information.
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.
PAGE AEP:NRC:0 ATTACHMENT 10 UMMARY DESCRIPTIONS FOR D.
C.
COOK UNI CYCLE 6 PROPOSED TECHNICAL SPECIFICATION PAGE SECTION DESCRIPTION REMARKS 2-5 Table 2.2-1 008 The allowable value for Overpower AT is directed to Note 4.
This value is revised to reflect the value used in the analysis for 10%
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.
009 Allowable value for loss of flow trip changed.
010 Design flow value in footnote is changed.
Change to 'provide greater consistency between units.
New value more conservative than current value and is supported by Attachment 3.
This value is changed to reflect the 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 2-7 Table 2.2-1 Table 2.2-1 (Note 1)
Oll Allowable value for steam generator low-low level trip changed.
012 "t" is replaced by "~" in the equation.
013 T's changed to < 574.1 F.
Changed to value resulting from new analysis of trip allowances performed by Westinghouse.
See Attachment 3.
Editorial change; to achieve greater consistency with STS, Rev.
4 and Unit 1 Technical Specifications.
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 4.1.1.2 3/4 1-3a; 3.1.1.2 3/4 1-3b 4 '.1.2 3/4 1-4 3.1.1.3 3/4 1-11 3.1.2.3.a 3/4 1-13 F 1.2.5 3/4 1-15 3.1.2.7 3/4 1-23 3.1.3.4 3/4 1-25 3.1.3.6 023 Revised to include MODE 4 and MODE 5 in the same specific-ation.
Revised Technical Specification requirements based on new dilution accident analysis in MODES 4 and 5.
024 Pages added due to length of new specification.
025 Footnote added.
026 Footnote added.
027 Footnote added.
028 Changed minimum RWST volume.
029 ACTION statement b removed.
030 Reference to Figure 3.1-2 is removed.
A new analysis of the dilution accident for MODES 4 and 5 was performed.
See section 15.4.6.3.1 of XN-NF-85-64(P) and Attachment 5.
Editorial change.
The Technical Specification boron conc-entration in the RWST is sufficient to provide adequate shutdown margin from expected operating conditions.
The Technical Specification boron conc-entration in the RWST is sufficient to provide adequate shutdown margain from expected operating conditions.
The Technical Specification boron conc-entration in the RWST is Sufficient to provide adequate shutdown margain from expected operating conditions.
A new analysis of dilution accident for MODE 5 was performed.
See Attachment 5 ~
Three loop opqeation in Modes 1 and 2
will be prohibited.
Three loop operation in Modes 1 and 2
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.
PAGE AEP NRC 0
ATTACHMENT 10 UMMARY DESCRIPTIONS FOR'D.
C.
COOK UNI CYCLE 6 PROPOSED TECHNICAL SPECIFICATION PAGE SECTION DESCRIPTION REMARKS 2-8 2-9 Table 2.2-1 (Note 1)
Table 2.2-1 (Notes 2,3,4) 014 The values of Kl, K2, and K3 are changed.
015 The definition of f (hI) is changed:
-40 percent. is changed to -31 percent and 1.8 percent is changed to 2.9 percent.
016 Parameters for three loop operation are removed.
017 T" is changed to < 574.1 F.
018 The definition of f (hI) is revised.
019 Note 3 is revised and Note 4
is added.
These values are revised to reflect the 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.
Most conservative values based upon Tables 15.0.7-2 and 15.0.7-3 of XN-NF-85-64 (P).
The OPL T and OTb T share one f(hI) module.
Three loop operation in Modes 1 and 2
will be prohibited.
This value is revised to reflect the value used in the analysis for 10%
steam generator tube plugging.
See Table 15.0.7-3 of XN-NF-85-64(P).
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.
Revisions to allowable values to permit operation with RdF RTDs.
See.
3/4 1-1 3.1.1.1 3/4 1-2 4 ~ 1. 1. 1. 1 020 APPLICABILITYchanged to MODES 1, 2, and 3.
021 Surveillance changed to MODE 3
only.
~4 Editorial cha~e to move MODE 4 SHUT-DOWN MARGIN Specification to Specification 3.1.1.2.
Editorial change to move MODE 4 SHUT-DOWN MARGIN Surveillance to Surveill-ance 4.1.1.2.b.
4 ~ 1.1.1.2 4 '.1.1.3 022 Add shutdown margin surveillance.
This surveillance required in Section 15.1.3.4 of XN-NF-85-28(P),
Supp. l.
AEP NRC UMMARY DESCRIPTIONS FOR D.
C.
COOK UN ATTACHMENT 10 CYCLE 6 PROPOSED TECHNICAL SPECIFICATIO PAGE PAGE SECTION 3/4 2-2 3.2.l.a.2.c 3/4 2-3 4
2 ~ 1 3
4.2 '.4 3/4 2-5 3.2.2 3-2 ' '
DESCRIPTION 032 Exemption from AFD requirements for APDMS calibration is removed.
033 F
(Z) is changed to APL.
M R8ferenced specification number has changed.
034 The F limit values of 2.04 and 4.08 8re changed to 2.10 and 4.20 respectively for Exxon Nuclear Co. fuel.
035 Description of F (Z) penalties moved from surveillance to LCO.
036 "where" removed from definition "and" removed from definition of K(Z).
037 Modified ACTION existing state-ment a.l to remove the require-ment to lower the Overpower bT (OPAT) in hot standby.
038 ACTION 3.2.2.a.2
-is removed.
The Axial Power Distribution Monitoring System (APDMS) is not used.
The plant will operate below the Allowable Power Level (APL).
The combined F (Z) target flux surveillance c8anged to combined APL-target flux surveillance.
See Technical Specification 3.2.6.
This reflects new F limits from XN-NF-85-68(P):"Donald C.
Cook Unit 2 Limiting Break LOCA/ECCS Analysis, 10%
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).
Editorial change for clarity.
Editorial change for clarity.
In the current Technical Specification 3.2.2, ACTION a.l requires that the OPAT trip setpoint reduction be per-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.
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 3/4 2-7 039 Much of this surveillance requirement has been moved to APL Specification 3.2.6.
Specification is simplified.
The PDC-II requirements that were in this 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 2.10 from 2.04 for Exxon Nuclear Co. fuel.
This reflects new F limits from XN-NF-85-68(P):"DonRld C.
Cook Unit 2 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 2-9 3/4 2-10; 3/4 2-11; 3/4 2-12 3'.3 4.2.3.1 Figure 3.2-4 Figure 3.2-5 041 These Technical Specifications are converted to Unit 1 Technical Specification format.
Flow rate and F
are separated in the Technical SpeciBcations to achieve 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 Tables 15.0.3-1 of XN-NF-85-64(P) and 3.5 of XN-NF-Q-68(P) for FhH
PAGE AEP:NRC:
I ATTACHMENT 10
SUMMARY
DESCRIPTIONS FOR D.
C.
COOK UNIT 2 CYCLE 6 PROPOSED TECHNICAL SPECIFICATIONS PAGE SECTION DESCRIPTION REMARKS 3/4 2-15 3.2.5 '
4.2.5 '.2 4'.5 '.3 4 ~ 2 ~ 5 ~ 1.4 3 '.5.1 4 '
gal.1 4'.5 '.2 4 ' '.1.3 4 ' '.1
~ 4 042 Reactor Coolant System Total Flow Rate is added as a
DNB limit.
043 These surveillance require-ments are added for the RCS Total Flow Rate.
Converted to the Unit 1 Technical Specification format.
044 4.0.4 exemption is added for flow specifications.
045 Specifications 3.2.5 and 4.2.5 have become 3.2.5.1 and 4.2.5.1.1, respectively.
Specification 3.2.5.1 is retitled.
Flow rate and F
are separated in the Technical SpeciHcations to achieve 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.
Flow surveillance requirements are taken from the old F>
Technical Spec-ification.
Clarificalions are added to the surveillance requirements.
Primary flow instrumentation is calibrated at or near full power.
Editorial change; this reflects the addition of" a new DNB specification 3.2.5.2 and the addition of surveill-ance requirements for 3.2.5.1.
PAGE DESCRIPTION AEP:NRC:
I ATTACHMENT 10
SUMMARY
DESCRIPTIONS FOR D. C.
COOK UN 2
CYCLE 6 PROPOSED TECHNICAL SPECIFICATIO S
PAGE SECTION REMARKS 3/4 2-16 Table 3.2-1 046 The parameters and footnotes for three loop operation are removed.
Three-loop operation in Modes 1 and 2
will be prohibited.
047 The value of RCS T is changed.
avg 048 RCS Total Flow Rate is added as a limit.
Made more consistent with the Unit 1 Technical Specifications.
New limit based on analysis for 104 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.
Flow rate and F
are separated in the Technical Speci8caticns.
The trade-off between flow and F<H is elimin-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.
Justifications for the conservatism in the flow allowance and use of RdF RTDs is contained in.
The relationship between analysis flow and Technical Specification flow is discussed in.
049 Allowance for readability included for pressure limit.
Technical Specification value remains the same.
Analysis value reduced by the value of the allowance.
The allowance was calculated consistently with footnote *~.
An increase in required flow to accom-odate a pressure readability allowance is de'scribed in Attachment 5.
Calcul-ation of thd'allowance for instrument error is discussed in Attachment 7.
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 3/4 2-17 3.2.5 '
4.2.5.2 3/4 2-18 Table 3.2-2 DESCRIPTION 051 Specification added.
052 Table added.
REMARKS The limits on pressurizer pressure and T
in Mode 2 or Mode 3 (with the r8ZStor trip breakers closed and the 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.
PAGE AEP:NRC:
I ATTACHMENT 10
SUMMARY
DESCRIPTIONS FOR D
C.
COOK UNzT 2 CYCLE 6 PROPOSED TECHNICAL SPECIFICATIO PAGE 10 SECTION DESCRIPTION REMARKS I
3/4 2-19; 3.2.6 3/4 2-20 053 This entire Technical Specification is changed to an Allowable Power Level (APL)
Technical Specification.
054 F~ Limit value changed from 2.04 to 2.10 for Exxon Nuclear Co. fuel.
The APDMS, an option in current Tech-nical Specifications, is not used.
The plant will operate below APL.
This 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.
This reflects new F limits from XN-NF-85-68(P):"Donald C.
Cook Unit 2 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)-
PAGE AEP:NRC:09 ATTACHMENT 10 Y DESCRIPTIONS FOR D. C.
COOK UNIT 2 CYCLE 6 PROPOSED TECHNICAL SPECIFICATIONS PAGE 11 SECTION DESCRIPTION REMARKS 3/4 3-2 Table 3.3-1 055 Power Range, Neutron Flux Item 2 Functional Unit has an added applicable mode:*.
The Plant Transient Analysis requires the Power Range, Neutron Flux Funct-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
3/4 3-4 Table 3.3-1 Item 20B 3/4 3-5 Table 3.3-1 Notation 056 References to three loop operation are removed.
057 Changed ACTION for functional units.
058 Reactor Coolant Pump Breaker Position Trip Above P-7 has an added exemption from 3.0.4 applicability.
059 Footnote ** is removed.
Three loop operation in Modes 1 and 2
will be prohibited.
To achieve greater consistency with
- STS, Rev.
4 and Unit 1 Technical Specifications.
To achieve greater consistency with STS, Revision 4.
Three loop operation in Modes 1 and 2
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.
3/4 3-8 Table 3.3-1 3/4 3-9 Table 3.3-2 3/4 3-11 Table 4.3-1 061 Action 9 is removed.
062 Converted Turbine Pressure setpoint portion of P-7 from 66 psia to 51 psig.
063 Response time is added for Pressurizer Pressure High Functional Unit.
064 Power, Range, Neutron Flux Functional Unit has an additional Channel Function Test (S/U(1)) and an additional mode in which surveillances are required:*.
065 Power, Intermediate, and Source Range Neutron Flux and Loss of Flow Single Loop Functional Units have added exemptions from Specification 4.0.4.
Over-power AT and Overtemperature hT Functional Units have added exemptions from Specification and f2 (~I) penalties.
Three loop operation in Modes 1 and 2
will be prohibited.
Editorial change.
Analysis-value from Table 15.0.7-1 of XN-NF-85-64(P).
Conservative Technical Specification value chosen to achieve greater consistency with Unit 1 Technical Specifications.
The Plant Transient Analysis requires the Power Range, Neutron Flux Funct-ional Unit to be operable.with the reactor trip system breakers in the closed position and the control rod drive mechanism capable of rod with-drawal.
See section 15.4.1.3 of XN-NF-85-28(P), Supplement 1.
Exemptions are provided for surveill-ances which must be performed in the applicable mode.
~I
AEP:NRC!0 ATTACHMENT 10 UMMARY DESCRIPTIONS FOR D.
C.
COOK UNIT CYCLE 6 PROPOSED TECHNICAL SPECIFICATION PAGE 13 PAGE 3/4 3-13 SECTION Table 4.3-1 Notation DESCRIPTION 066 Footnotes (8) and (9) are added.
REMARKS See remarks for 3/4 3-11 above.
3/4 3-15; 3/4 3-16; 3/4 3-17 3/4 3-18 3/4 3-19; 3/4 3-20 Table 3.3-3 067 References to three loop operation in Modes 1 and 2
are removed.
068 Reference to ggg footnote for Differential Pressure Between Steam Lines-High Functional Unit changed to gggg footnote.
Three loop operation in Modes 1 and 2
will be prohibited.
The Differential Pressure Between Steam Lines-High actuation differs from other ESF Actuation signals in 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.
PAGE AEP:NRC:0 ATTACHMENT 10
SUMMARY
DESCRIPTIONS FOR D.
C.
COOK UNIT 2 CYCLE 6 PROPOSED TECHNICAL SPECIFICATIONS PAGE 14 SECTION DESCRIPTION REMARKS 3/4 3-15; Table 3.3-3 3/4 3-16; (Cont'd) 3/4 3-17'/43-18; 3/4 3-19; 3/4 3-20 (Cont'd) 3/4 3-21 Table 3.3-3 Notation 069 References to the 1982 refueling outage are removed.
070 Steam Generator Water Level High-High Functional Unit has an added applicable mode:
071 Footnote gggg is added.
072 Footnote
$ is added.
Editorial change; the 1982 refueling outage has already occured.
Section 15.1.2.3 of the Disposition of
- Events, XN-NF-85-28(P), Supplement 1,
requires the Steam Generator Water LevelHigh-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.
See remarks for footnote gggg for pages 3/4 3-15 through 3/4 3-20.
Section 14.1.2.3 of the Disposition of
- Events, XN-NF-85-28(P), Supplement 1,
requires the Steam Generator Water LevelHigh-High Functional Unit to be operable when operating on the low flow feedwater preheating system.
Footnotes g and gg 073 Conditions for blocking safeguards actuations are added.
These conditihns are required in sect-ion 15.1.3.4 of XN-NF-85-28(P), Supp.l.
, PAGE SECTION REMARKS AEP:NRC 0916I ATTACHMENT 10
SUMMARY
DESCRIPTIONS FOR D.
C.
COOK UNIT 2 CYCLE 6 PROPOSED TECHNICAL SPECIFICATIONS PAGE 15 DESCRIPTION 3/4 3-2la Table 3.3-3 ACTION statements 3/4 3-22 Table 3.3-3 074 ACTION statements moved, from previous page to this new page.
075 Reworded Condition and Set-point, Function description for P-12 interlock.
076 Setpoint limit values are revised.
077 P-12 function description revised to remove reference to high steam line flow.
Editorial change; expanded table notation necessitates additional page.
This change clarifies the definitions of the interlock and makes the defin-ition less ambiguous.
Patterned after STS, Rev.4.
New limits are based on revisions to allowances to permit operation with RdF RTDs.
See Attachment 3.
Editorial change; safety injection actuation occurs on low steam line pressure only.
There has never been a
coincidence with high steam flow on-Unit 2.
PAGE DESCRIPTION AEP NRC:09 ATTACHMENT 10 UMMARY DESCRIPTIONS FOR D.
C.
COOK UNIT 2 CYCLE 6 PROPOSED TECHNICAL SPECIFICATIONS PAGE 16 REMARKS 3/4 3-25 Table 4.3-2 3/4 3-25a Table 4.3-2 3/4 3-32 Table 4.3-2 3/4 3-33 Table 4.3-2 3/4 3-38 3.3.3.2 4.3.3.2.c 3/4 3-48; 3.3.3.7 3/4 3-49 4.3.3.7 078 Allowable value of low-low T
changed.
079 Allowable values for auxiliary feedpump actuations on low-low steam generator level changed.
080 Steam Generator Water Level High-High Functional Unit has an additional required mode:
081 Loss of Main Feedwater Pumps Mode 3 Surveillance Requirement deleted.
082 Footnote
$ added for Steam Generator Water Level High-High Functional Unit.
083 References to the 1982 refuel-ing outage are removed.
084 The references to F are removed.
xy 085-This entire Technical Specification is removed.
Changed allowable value to be consist-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.
Changed to value resulting from new analysis of trip allowances performed by Westinghouse.
See Attachment 3.
Section 14.1.2.3 of the Disposition of
- Events, XN-NF-85-28(P),
Supplement, 1,
requires the Steam Generator Water LevelHigh-High Functional Unit to be operable when operating with the main feedpumps feeding the steam generators in Modes 3 and 4.
Editorial change; Mode 3 applicability for Loss of Main Feedwater Pumps was deleted from Table 3.3-3 in Unit 2 License Amendment 477.
See remark for p 3/4 3-32 above.
~I The 1982 refuel.ing outage has already occured.
Editorial change; F
is not used for core monitoring witPPDC-II.
The APDMS is not used.
The plant will operate below APL.
PAGE AEP NRC:0 ATTACHMENT 10 UMMARY DESCRIPTIONS FOR D. C.
COOK UNIT 2 CYCLE 6 PROPOSED TECHNICAL SPECIFICATIONS
'PAGE 17 DESCRIPTION REMARKS 3/4 4-2 3.4.1.2.b 3.4.1.2.c 3.4.1.2 ACTION b Footnote **
086 Criteria for the operability of reactor coolant loops are estab-lished based on the status of the reactor trip system breakers and/or the control rod system.
087 ** is added to ACTION b; footnote added at bottom of pageos The Plant Transient Analysis requries these changes based on the uncontrolled control rod bank withdrawal from subcritical.
See section 15.4.1.1 of XN-NF-85-64(P).
The Technical Specification boron concentration in the RWST is suff-icient to provide adequate shutdown margin from expected operating conditions.
3/4 4-2a 3/4 4-3 3/4 4-3a 4.4 ~ 1.2.1 4 ~ 4 ~ 1.2.2 3.4.1.3 ACTION b Footnote ***
088 Surveillances moved from previous page.
089 ****is added to ACTION b; footnote ****is added on p 3/4 4-3a.
090 ACTION statements moved from.
page 3/4 4-3 to page 3/4 4-3a.
Editorial change; additional text requires moving this material.
The Technical Specification boron concentration in the RWST is suff-icient to provide adequate shutdown margin from expected operating conditions.
Editorial change; additional footnote requires moving this material.
PAGE AEP:NRC:09 ATTACHMENT 10
SUMMARY
DESCRIPTIONS FOR D. C.
COOK UNIT 2 CYCLE 6 PROPOSED TECHNICAL SPECIFICATIONS PAGE SECTION DESCRIPTION REMARKS 18 3/4 4-3bi 3/4 4-3c; 3/4 4-3d 3 ~ 4 ~ 1.4 4.4.1.4 091 The entire Technical Specification is removed.
ACTION statements of Technical Spec-ification 3.4.1.4 are currently 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 is added.
093 Page 3/4 4-4 is submitted as a back page to a blank 3/4 4-3b.
Section 15.5.1 4 of the Disposition of
- Events, XN-NF-85-28(P), Supplement 1,
requires this action to prevent overpressurization due to an inadvertent increase in the RCS inventory.
This eliminates the need to submit blank pages for pages 3/4 4-3c and 3/4 4-3d.-
PAGE SECTION AEP:NRC: 0 ATTACHMENT 10 UMMARY DESCRIPTIONS FOR D. C.
COOK UNIT CYCLE 6 PROPOSED TECHNICAL SPECIFICATION PAGE 19 DESCRIPTION REMARKS 3/4 4-32 3.4.11 3/4 4-33
- 4. 4. 11. 1 4.4.11.3 094 "operator" changed to "operated" 095 ACTION changed to only allow one PORV or block valve inoper-able.
Making more than one PORV inoperable without shutting down the reactor is not allowed.
096 References to Section 6.9.1.9 are deleted.
097 Portions of expanded ACTION statement and surveillance requirements moved to p 3/4 4-33.
098 References to surveillances in other sections changed.
Editorial change; to use proper termin-ology.
NRC staff comments at December 13, 1984, meeting; the proposed changes are intended to ensure that the PORVs are available to assist in RCS depressur-ization following a steam generator tube rupture without offsite power.
To achieve greater consistency with
Editorial change; surveillance requirement moved from previous page to this page.
Editorial change; the current refer-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 3/4 7-3 Table 3.7-2 3/4 7-5 4.7.1.2 099 ACTION b is modified to remove three loop operation in Modes 1
and 2.
100 Table is removed.
101 Discharge pressures for aux-iliary feedwater pump flow testing changed.
Three loop operation in Modes 1 and 2
will be prohibited.
Three loop operation in Modes 1 and 2
will be prohibited.
The value for pump discharge pressure is adecpxate to assure that in the event 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).
PAGE AEP:NRC:09 ATTACHMENT 10 UMMARY DESCRIPTIONS FOR D.
C.
COOK UNIT CYCLE 6 PROPOSED TECHNICAL SPECIFICATION PAGE 21 SECTION DESCRIPTION REMARKS 3/4 7-10 3.7.1.5 4.7.1.5 3/4 9-8 3 ' '.1 3/4 10-2 4.10 ' '
102 ACTION statements are revised.
103 Exemption from Specification 4.0.4 is added for entry into Mode 3.
104 Footnote
- is added.
105 Referenced specifications are renumbered.
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.
Exemptions are provided for surveill-ances which must be performed in the applicable mode.
The Technical Specification boron concentration in the EST is sufficient to provide adequate shutdown margin from exepected operating conditions.
Editorial change; reflects simplifica-tion of F and APL specifications, 3.2.2 and 3.2.6 respectively.
See page 3/4 2-6.
PAGE SECTION DESCRIPTION AEP:NRC:09 UMMARY DESCRIPTIONS FOR'.
C.
COOK UNIT ATTACHMENT 10 CYCLE 6 PROPOSED TECHNICAL SPECIFICATIONS PAGE REMARKS 22 B 2-1 B 2-4 2.1.1 (Bases) 2 ~ 2 ~ 1 (Bases) 106 References to Figure 2.1-2 are removed.
107 Revision made to the basis of negative rate trip.
Three loop operation in Modes 1 and 2
will be prohibited.
Reference was made to the "Interim 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 hT (Bases) three loop operation is removed.
Three loop operation in Modes 1 and 2
will be prohibited.
B 2-5 B 2-6 B 2-6 B 2-6 B 2-7 2.2.1 (Bases) 2.2.1 (Bases)
Loss of Flow (Bases) 2 ~ 2 ~ 1 (Bases) 109 Corrected spelling of the word "operation".
110 Added reference to f(~I) penalty for OPzT.
illAdded reference to the use of the pressurizer pressure high trip in the loss of load event.
112 Moved text from page B 2-6 to B 2-5.
113 The value of P-8 is changed to 314.
114 Design flow is defined and used instead of nominal flow.
115 References to three loop operation are removed.
=116 Moved text from page B 2-7 to B 2-6.
Editorial change.
Cycle 6 analysis requires f(b,I) penalty for OPDT trip.
See Table 15.0.7-3 of XN-NF-85-64(P).
This function was used in the Cycle 6
analysis.
See section 15.2.1.3 of XN-NF-85-64(P)
~
Editorial change.
Editorial change.
Revision describes Exxon DNB methodology.
P'hree loop operation in Modes 1 and 2
will be prohibited.
Editorial. change.
PAGE SECTION DESCRIPTION AEP:NRC:09 Y DESCRIPTIONS FOR D. C.
COOK UNIT ATTACHMENT 10 CYCLE 6 PROPOSED TECHNICAL SPECIFICATIONS PAGE 23 REMARKS B 3/4 l-l Shutdown 117 Revision to Shutdown Margin Margin (Bases)
Basis.
Describes Exxon analyses of steam dump 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 B 3/4 1-2 (Bases)
B 3/4 1-2 Moderator Temperature Coefficient-(Bases)
Minimum Temp. for Criticality (Bases)
B 3/4 1-3 3/4.1.2 (Bases) 118 Moved text from B 3/4 l-l to B 3/4 1-2.
119 Revision to Moderator Temper-ature Coefficient (MTC) basis.
120 Revised discussion of inter-action between minimum temperature for criticality requirement and P-12 reset point.
121 Revisions were made to desc-ription of the RWST as a
boration source.
Editorial change.
Revised material describes Exxon MTC methodology.
Bases were revised to more accurately reflect the operation of P-12 reset point.
PAGE SECTION DESCRIPTION AEPeNRC'09 UMMARY DESCRIPTIONS FOR D. C.
COOK UNIT ATTACHMENT 10 CYCLE 6 PROPOSED TECHNICAL SPECIFICATIONS PAGE 24 REMARKS B 3/4 2-1 Power Distrib-122 The F limit value of 2.04 ution Limits is chRnged to 2.10 for (Bases)
Exxon Nuclear Co. fuel.
123 Tube plugging percentages are changed.
124 Cycle 5 margin reference deleted.
125 Comma added.
126 "increase" changed to "increased" This reflects new F limits from XN-NF-85-68(P):"Donald C.
Cook Unit 2 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 2.2 of XN-NF-85-68(P)
Future use of Westinghouse fuel expected to be minimal.
Editorial change; grammatical error.
Editorial change; typographical error.
Axial Flux Difference (Bases)
B 3/4 2-4 3/4.2.2 3/4 '.3 (Bases) 127 The F limit value of 2.04 is changed to 2.10 for Exxon Nuclear Co. fuel.
128 RCS flowrate is removed from these specifications.
NIncluding revised statement on F>H measurement error.
129 References to F and F>
expanded to include pro)need APL Technical Specification.
This reflects new F limits from XN-NF-85-68(P):"Donald C.
Cook Unit 2 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).
Flow rate and F
.= are separated in the Technical SpeciHcations.
The trade-off between flow and F>H is eliminated.
See Table 15.0.3-1 of XN-NF-85-64(B) and Table 2.1 of XN-NF-85-68(P)P Editorial change.
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 (Bases) 130 Revisions made to basis to distinguish between modes and refer to safety analysis.
131 RCS flowrate added to this specification, including discussion of surveillances.
132 Revised discussion of read-ability allowances to include pressurizer pressure and flow.
133 "thru" becomes "through".
Editorial changes.
RCS flowrate is now a DNB parameter.
New allowance included for pressurizer pressure.
Flow added to DNB specific-ation.
See Attachment 3 and.
Editorial change; typographical error correction.
3/4.2.6 (Bases) 134 Added paragraph describing DNB limits for Modes 2 and 3.
135 This section is changed to an Allowable Power Level (APL)
Technical Specification.
The limits on pressurizer pressure and 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).
-The APDMS is not used.
The plant will
- operate below APL.
B 3/4 3-1 3/4.3.1 3/4 ' '
(Bases) 136 Basis material added describing main feedpump operation in Modes 3 and 4 and the conditions for blocking ESF actuation.
Protection required for operation with a main feedpump feeding steam generators in Modes 3 and 4 is 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).
PAGE DESCRIPTION REMARKS AEP:NRC:0916I ATTACHMENT 10
SUMMARY
DESCRIPTIONS FOR D.
C.
COOK UNIT 2 CYCLE 6 PROPOSED TECHNICAL SPECIFICATIONS SECTION PAGE 26 B 3/4 3-li 3/4 ~ 3 ~ 3.1 B 3/4 3-2 (Bases)
B 3/4 3-2 3/4 ' ' '
(Bases)
B 3/4 4-1 3/4.4.1 (Bases)
B 3/4 4-la 3/4.4.2 3/4.4.3 (Bases)
B 3/4 4-11 3/4.4.11 3/4.4.12 (Bases)
B 3/4 7-1 3/4.7.1.1 (Bases)
B 3/4 7-2 3/4 ~ 7.1 (Bases) 137 Basis 3/4.3.3.1.
moved to page B 3/4 3-2.
138 This section is removed.
139 References to three loop operation are removed.
140 Additional operable loop is required with control rods capable of withdrawal.
141 All Safety Injection pumps and all but one charging pump will be rendered inoperable in Modes 4 and 5 if no safety valves are operable to prevent overpressurization due to an inadvertent increase in the RCS inventory.
142 Period converted to /.
143 References to three loop operation are removed.
144 Reference to Table 3.7-2 is changed to Table 3.7-1.
This basis is condensed to one page.
145 Variable definitions are moved to previous page.
Editorial change.
The APDMS is not used.
The plant will operate below APL.
Three loop operation in Modes 1 and 2
will be prohibited.
The Plant Transient Analysis requires these changes based on the uncont-rolled control rod bank withdrawal from subcritical.
See section 15.4.1.1 of XN-NF-85-64(P).
See Section 15.5.1.4 of the Disposition of Events, XN-NF-85-28(P),
~
Supplement l.
Editorial change.
Three loop operation in Modes 1 and.
2 will be prohibited.
Editorial change; incorrect table reference.
Editorial change; improve readability.
~ '