ML20195H911
| ML20195H911 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 01/15/1988 |
| From: | Counsil W TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| TXX-88040, NUDOCS 8801200410 | |
| Download: ML20195H911 (119) | |
Text
M EE Log # TXX-88040 File # 10010
=. __
r r Ref # 10CFR50.34(b) illELECTRIC wn.. c. co na January 15, 1988 cmwnma rra,aa,,a U. S. Nuclear Regulatory Commission 7 ATTN: Document Control Desk '
Washington, D. C. 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-415 AND 50-446 FSAR AMENDMENT 6C DESCRIPTION REF: TV Electric Letter TXX-6999 from W. G. Counsil to U.S.N.R.C. dated December 23, 1987.
Gentlemen:
Amendment 66 to the CPSES FSAR was transmitted to you under a separate cover letter, TXX 88041, dated January 15, 1988. ,
Some of the figures, and in particular, flow diagrams, which will be updated in Amendment 66 are not included in this enclosure. Another TV Electric letter will be issued to submit copies of the figures and flow diagrams.
Amendment 66 provides updates, clarifications, revisions, corrections, '
additions and editorial changes to the FSAR as well as a revised Effective Page Listing for the affected portions of the report. Listed below is a summary of some of the more significant changes and the known disparities (noted by an "*") between the advanced draft copy (see reference) and this submittal of Amendment 66:
1.0 INTRODUCTION
AND GENERAL DESCRIPTION OF PLANT (ATTACHMENT 1) 1.2.2 Plant Description A change to the technical description of the Fire Protection Water Supply System to reflect the final as-built plant design. Includes the new Fire Water Supply description and the use of engineering evaluations in the Fire Protection '
Program.
P A change to the containment plar and fuel building overhead
. cranes. This update affects the engineering design of the Single Failure Proof (SFP) cranes and hoists.
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TXX-88040 January 15, 1988 Page 2 of 11 1A(N)/lA(B) Discussion of Regulatory Guides TV Electric's positions on the following Regulatory Guides have been changed to provide clarification, response to new revisions or alternative approaches to satisfy regulations:
1 Regulatory Guide 1.13 2 Regulatory Guide 1.19 3 Regulatory Guide 1.46 4 Regulatory Guide 1.48 5 Regulatory Guide 1.52 6 Regulatory Guide 1.53 7 Regulatory Guide 1.67 8 Regulatory Guide 1.68 ,
9 Regulatory Guide 1.70 10 Regulatory Guide 1.75 11 Regulatory Guide 1.105 12 Regulatory Guide 1.129 13 Regulatory Guide 1.131 14 Regulatory Guide 1.137 2.0 SITE CHARACTERISTICS (ATTACHMENT 2) 2.2.3 Evaluation of Potential Accidents
- A change to correct the value stated for the elevation dif ference between the control room air intakes and the circulating water chlorine storage location.
2.3.1 Regional Meteorology A change that deletes the wind velocity information from Section 2.3 because it is discussed in Section 3.3.
2.4.12 Dispersion, 911ution, and Travel Time of Accidental Releases of Liquid Effluents in Surface Waters A change for clarification of controlled releases from Squaw
- Creek Reservoir as required by TDWR Permit No CP-20, 3.0 DESIGN OF STRUCTURES. COMPONENTS. E0VIPMENT. AND SYSTEMS (ATTACHMENT 31 3.3.1 Wind Loadings A change to indicate that all seismic Category I structures have sufficient capacity to withstand tornado and wind loadings.
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TXX-88040 January 15, 1988 Page 3 of 11
- A change to delete doors that are no longer required for Fire Protection in accordance with the latest revision of the Fire Hazard Analysis Drawings.
3.5.3 Barrier Design Procedures
- A change to correct the limiting ductility ratio for steel columns which determine the overall response of structural barriers to missile impact.
3.68.2 Determination of Break Locations and Dynamic Effects Associated with the Postulated Rupture of Piping (Inside and Outside Containment)
- A change that deletes reference to selution of breaks at intermediate locations based on potential high stress points. The application cf the sum of squares equations indicated in ASME Section III is now used for the determination of all intermediate break locations for Class 2 and 3 piping.
Changes in the use of computer codes as follows:
- 1) Replaces computer programs and reflect the use of improved computer code versions,
- 2) Adds computer codes that may be used for determination of piping dynamic response,
- 3) Revises modeling computer codes, and
- 4) References the use of applicable computer codes.
A change that describes the new methodology used to determine jet impingement loads. The primary differences between the new method and the previous method are in, 1) the jet expansion model, and 2) the use of jet attenuation factors.
A changt that deletes the reference to pipe whip restraint design for RCS main loop piping which is a result of the application of the leak-before-break technology permitted in GDC-4.
3.8.3 Concrete and Steel Internal Structures of Steel or Concrete Containment The discussion of polar crane derailment is clarified in regard to load combinations.
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TXX-88040 January 15, 1988 ,
Page 4 of 11 '
4.0 REACTOR (ATT.',CHMENT 41 4.2.4 Testing and Inspection Plan A change to provide a clear description # Loose Parts Monitoring Syst.m installation.
4.4.5 Testing and Verification A change to reflect current testing mathodology for obtaining reactor coolant flow maasurement.
5.0 REACTOR COOLANT SYSTEM (ATTACHMENT 5) 5.2.3 Reactor Coolant Iressure Boundary Materials A change that revises the closure hard. tare for the Pressurizer and Steam Generator manways and updates the primary chemistry parameters.
Reactor Coolant kater Chemistry specifications updated.
5.4.14 Component Supports A change to revise text and figures concerning removal of RCS restraints resulting from application of the leak-
- efore-break technology.
6.0 ENGINEEREU SAFETY FEATURES (ATTACHMENT El t, . 2. 4 Containment Isolation System A change to update the containment isolation provisions.
Changes to the tables add existing valves that were previ'ausly omitted. Various Note (s) to the tables have been revised, clarified, updated and deleted.
6.2.5 Combustible Gas Control in Containment A change to revise the post-LOCA hydrogen production rate resulting from the reevaluation of design criteria and calculations.
6.2.6 Containment Leakage Testing A change to clarify leak rate testing criteria.
TXX-88040-January 15, 1988 Page 5 of.11 6.4.1 Design Bases A change that revises the allowable beta skin dose for control room occupants during a LOCA. The allowable skin dose may be increased when special protective clothing and eye protection is used.
6.5.1 Engineered Safety Feature (ESf) Filter System A change to clarify the design of safety-related ductwork for the specific allowable leakage rates.
6.5.2 Containment Spray System A change to revise the containment spray model.
7.0 INSTRUMENTATION AND_CDSTROLS (ATTACHMEET 7) 7.1.2 Identification of Safety Criteria A change to clarify the distinction between NSSS and B0P Class lE Uninterruptible Power Supplies (UPS).
7.3.1 Description (Engineered Safety Features Systems)
A change to delete the Auxiliary Feedwater Pumps low pump suction pressure as an interlock.
7.4.1 Description (Systems Required for Safe Shutdown)
A change to add "Train B" transfer switches into the discussion of electrical isolation of components between the Hot Shutdown Panel (HSP) and Control Room circuits.
i A change to add the Control Room HVAC Mechanical Equipment Room to the description of Alternate Shutdown Areas.
7.5 Information Systems Important to Safety These changes to the text and tables have been made to
- correct and clarify the applicability of Regulatory Guide i 1.97, Rev. 2, to be consistent with the as-built plant
! design, the SER and supplements and the post-THI requirements. Additional information (i.e., notes and deviations) has been provided to clarify the CPSES position in areas of ambiguity.
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1 TXX-88040 l January 15, 1988 l Page 6 of 11 8.0 ELECTRIC POWER (ATTACHMENT 8)
Sections 8.1 (Introduction), 8.2 (Offsite PNer System) and 8.3 (Onsite Power Systems)
The major changes to Sectione 3.1, 8.2 and 6.3 are to reflect the addition of two startup transformers to feed the non safety-related 6900-V buses. This design modification improves the offsite power system reliability by 1) separating the non safety-related 6900-V buses from the safety-related 6900-V buses, 2) reducing the load requirements on the startup transformers, and 3) reducing the influence of grid related voltage fluctuations.
The AC Essential Lighting System and DC Emergency Lighting System are reclassified as non-Class IE. The AC Essential Lighting System is fed from safety-related buses and isolated from them with two separate, coordinated Class IE breakers connected in series. The DC Emergency Lighting System will now be fed from dedicated non-Class IE batteries. The reclassified circuits are routed in conduit to provide physical and electrical independence from Class IE circuits. This change also impacts FSAR Sections 1.2.1, 9.5, and 17A.
9.0 AUXILIARY SYSTEMS (ATTACHMENT 9) 9.2.2 Corponent Cooling Water System 1
A change that adds CCW regulating valves which control CCW flow to/around the Ventilation Condensers based on a pressure indicating controller on the refrigerant side of the condenser.
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Revised the Chilled Water System condenser control to l
automatic control, actuated by refrigerant pressure.
( 9.2.3 Demineralized and Reactor Makeup Water System A change to reflect the addition of the demineralized water source to perform turbine generator primary flow rate testing during refueling outages.
9.4 Air Conditioning, Heating, Cooling, and Ventilation System l
A change to the non safety-related Chilled 9ater System to l add cooling capacity.
A change to the indoor design conditions for various plant areas.
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TXX-88040 January 15, 1988 Page 7 of 11 A change to revise and clarify the iodine adsorber design parameters.
- Figure 9.4-6 was submitted without reflecting the containment pentrations Diping test connections as "locked closed." Also, Figure 9.4-11 (sheet 2) was submitted without reflecting the addition of the relief valves. These Figures are now correct as described and indicated in the amendment.
9.5 Fire Protection System This change includes the new Fire Water Supply description and the use of engineering evaluations in the Fire Protection Program. Also, this change includes the use of radios as the primary means of communication during an emetgency.
10 ' ; TEAM AND POWER CONVERSION SYSTEM (ATTACHMENT 101 10.3 Itain Steam Supply Charge; to reflect the modification that replaced the MSIV bus Valves with manual valves.
A change to clarify that Steam Generator PORVs have air accumulators.
10.4.9 Auxiliary Feedwater System Changes that reflect design parameters for AFW components.
11.0 RADI0 ACTIVE WASTE MANAGEMENT (ATTACHMENT 111
- 11.3.2 System Description Changes to the description of the Gaseous Waste Processing System to allow for greater operational flexibility.
A change to the Resin Disposal System to allow for greater orerational flexibility.
12.0 RADIATION PROTECTION (ATTACHMENT _ill 12.2.1 Contained Sources A change to delete the equipment qualifir 1 tion dose evaluations from the initial shield design calculations.
TXX-88040 January 15, 1988 Page 8 of 11 12.3.4 Area Radiation and Airborne Radioactivity Monitoring Instrumentation A change to modify setpoint bases for detection of significant releases, long-term surveillance, and emergency plan actuation.
13.0 CONDUC1 0F OPERATIONS Text changes for Sections 13.1, Organizational Structure of Applicants; 13.4, Review and Audit; and 13.5, Plant Procedures and Instructions; were inadvertently submitted in the advanced draft copy of the FSAR Amendment 66. These text changes are not included as part of this amendment, but will be submitted in a future amendment.
14.0 INITIAL TEST PROGRAM (ATTACHMENT 14) 14.2 Initial Test Program Text changes for Section 14.2 regarding initial startup testing, the startup and test group, joint test group, and Unit 1 prestart test program were inadvertantly submitted in the advance draft copy of FSAR Amendment 66. These text changes are not included as part of this amendment, but will be submitted in a future amendment.
14.2.12 Individual Test Descriptions (Preoperational Tests)
Table 14.2-2 was changed to revise the test method to demonstrate the performance of the ESF pump room coolers.
15.0 ACCIDENT ANALYSIS (ATTACHMENT 15)
- Offsite dose consequences of certain accidents have been i recalculated using the source terms from Revision 3 of the Westinghouse "Radiation Analysis Design Manual."
15.1.5 Steam System Piping Failure This change includes iodine spike analysis in the radiological consequences due to main steam line break in j accordance with Section 15.4.5 of the Standard Review Plan.
15.6.5 Loss of Coolant Accidents Resulting From a Spectrum of l
Postulated Piping Breaks Within the Reactor Coolant Pressure Boundary This change is the deletion of the radiological consequences due to containment purging of hydrogen in accordance with Section 15.6, Appendix C, of the Standard Review Plan.
TXX-88040 January ~15, 1988 Page 9 of 11 15.7.4 Design Basis Fuel Handling Accidents A change to reanalyze the radiological consequences using an irradiated fuel assembly that had decayed for 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, per Regulatory Guide 1.25.
17.0 OVALITY ASSURANCE 17A.1 Scope of QA Applicability The changes to Table 17A-1 are technical in nature and do not affect the programmatic aspects for the establishment and implementation of the QA/QC programs.
RESPONSE TO NRC ACTION PLAN DEVELOPED AS A RESULT OF THE THI-2 ACCIDENT II.K.3 Final Recommendations of B&W Task Force A change to eliminate the derivative action associated with the pressurizer PORV Proportional Integral Derivative Controller Modification (PID).
NRC OVESTIONS AND RESPONSES (ATTACHMENT 181 Changes to the following questions and responses (Section) have been made for clarification, correction, update, and addition:
- 1) 010.0 Auxiliary Systems Branch
- 2) 022.0 Containment Systems Branch
- 3) 032.0 Instrumentation and Control Systems Branch
- 4) 040.0 Power Systems Branch
- 5) 112.0 Mechanical Engineering Branch
- 6) 220.0 Analysis Branch / Systems Analysis
- 7) 372.0 Hydrology - Meteorology Branch
- 8) 421.0 Quality Assurance EDITORIAL Several editorial changes which include the reissuance of Sections, Appendices, Tables and Figures utilizing the format allowing computerization of the amendment change bars and numbers. This computerization ensures consistency and
! accuracy of the FSAR.
I A page-by-page description of the changes is attached (See Attachments 1 through 19). Pages which do not have changes but are included in the amendment (either because they are on the opposite side of the sheet from a page that was changed or because a change shifted the existing material to a new page) are not discussed in the attachments.
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TXX-88040 January 15, 1988 l Page 10 of 11 )
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In addition to the foregoing FSAR Amendment 66 changes, TU Electric anticipates further CPSES changes resulting from additional modifications to the CPSES design and/or physical plant. While the details of these changes are not sufficiently defined to include them in 'Tendment 66 to the CPSES FSAR, we would like to supply the staff with advance notice of the potential for such changes. These potential changes are noted below with a hrief description:
- 1) 138kV Transmission Line ,
l CPSES intends to install an additional 138kV transmission line and a 138kV switch yard. This line will improve the reliability of the offsite electric power supply system and will allow operational flexibility for transmission line maintenance. There will be no significant environmental impact since the new line will use existing right-of-ways and the area previously set aside for use as a future switchyard. The design will maintain the GDC-17 offsite power source requirements.
- 2) Leak-defore-Break for Branch Lines CPSES intends to apply the recently approved broad scope rule change to GDC-4 regarding the elimination of the dynamic effects for certain branch line breaks based on the leak-before-break technology. This is an extension of the leak-before-break technology that was applied to the main reactor coolant loops at CPSES as approved by the NRC.
The screening of lines for application of this change will conform to the draft SRP 3.6.3 currently published for comment.
- 3) Sut,-compartment Analyses The containment sub-compartments are being reanalyzed, in part because of the use of leak-before-break methodology for branch lines as described above. Although no unacceptable results are expected from these reanalyses, many tables and figures in Section 6.2 of the CPSES FSAR will be revised.
- 4) Amplified Response Spectra The Amplified Response Spectra (ARS) are being updated to support the seismic qualification of the Servica Water Intake Structure (SWIS).
CPSES FSAR (Section 3.7) is being updated to clarify the Category I
! building seismic analysis. For the SWIS and Category I tanks, a revised ARS is required. The new ARS for the SWIS and Category I tanks will be discussed in an upcoming amendment to the CPSES FSAR.
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TXX-88040 January 15, 1988 Page 11 of 11
- 5) Protective Re7ay System Due to the Station Service System modifications, changes will be required to the Protective Relay System in the FSAR. These changes include relay settings for primary and backup under voltage protecticn. Since the results of the Station Service System modifications are just now being determined, there is insufficient time to properly revise the relay. settings prior to issuance of FSAR Amendment 66. These relay changes will be prepared after January 1, 1988.
Very truly yours, MM W. G. Counsil DAR/dar Attachment c- Mr. R. D. Martin, Region IV CPSES Resident Inspectors - 3 copies t
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Attachment 1 to-TXX-88040 !
January 15, 1988 l Page 1 of 7 !
CPSES FSAR AMENDMENT 66 DETAILED DESCRIPTION l l
FSAR Page 1 (as amended) Description 1.2-15 V)date: An editorial change to reflect the addition of tie Comanche Switch transmission line (provided in Amendment 60).
1.2-23 Clarification: Clarifies the ex)lanation of fixed Fire Suppression Systems throughout t1e plant by deleting the word "deluge" from the term "Deluge Water Spray System".
The technical basis of the Water Spray System design is unaffected.
1.2-24 Clarification: This change clarifies the explanation of fire detector by adding "unless the system is designed strictly for mancal operation." 'The technical basis of the detection system is unaffected.
1.2-26 Clarification: Changes the technical description of the Fire Protection Water Supply System to reflect the final as-built Plant Fire Protection Water Supply System design. The final design utilizes two, greater than 100's capacity, dedicated fire water storage tanks and three, 50's capacity, fire pumps independently connected to the underground yard main loop. The tank, pump and valve arrangement facilitates suction from either ce both tanks. There are two diesel engine driven fire pumps and one electric motor driven fire pump housed in a structure protected by automatic sprinklers and detection.
1.2-28 See Justification for page 1.2-23.
Table 1,3-2 Editorial: The table is being reissued as a result of some text shifts between pages.
(Sht. 22) Revision: The AC Essential Lighting System and DC Emergency Lighting System are being reclassified as non-Class 1E (See Justification for page 1A(B)-45).
Table 1.6-1 Editoricl: The table is being reissued in the computerized format.
(Sht. 17) Correction: The deletion of reference to WCAP 9198, "Reactor Vessel Head Drop Analysis", is required. The SFP capabilities of the containment polar cranes make '
reference of this WCAP inappropriate. Also, this WCAP is not applicable to CPSES.
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Attachment 1 to TXX-88040 January 15, 1988 Page 2 of 7 FSAR Page (as amenaed) Description 1A(N)-31 Revision: Clarification to reflect that CPSES 80P systems meet the single failure criterion as specified in Regulatory Guide 1.53.
1A(N)-57 and Revision: Regulatory Guide 1.105, Rev. 2 endorses ISA-1A(N)-58 S67.04-1982 in which design criteria for selecting safety-related setpoints are better defined and have been utilized in CPSES B0P safety-related setpoint calculations. This change revises the CPSES commitment from Revision 1 to Revision 2 of this Regulatory Guide.
The descriptions are adjusted based on this change.
lA(B)-6 Clarification: This change clarifies the NRC Regulatory Guide 1.13 discussion to indicate that the normal 31 ant exhaust filtration system operates continuously, w1ich includes during a fuel handling accident. The design was not changed but the previous description was not clear.
lA(B)-8 Correction: Provides a clearer description of how Regulatory Guide 1.19 is complied with.
Regulatory Guide 1.19 was developed as there were no directly applicable industry codes that covered the nondestructive examination of the containment steel liner and penetration welds in concrete containments. The regulatory staf f developed, in Regulatory Guide 1.19, acceptable standard procedures for the nondestructive examination of such welds. These procedures provided a uniform quality level consistent with the safety function of containment liners.
Both AC1 and ASHE recognized that a stwdard set of rules and requiroments were required to be developed to govern the design, materials, fabrication, erection, testing, and examination of concrete reactor vessels and containments. In accordance with this recogniticn an "ACI-ASME Technical Committee on Concrete Pressure Components for Nuclear Service" developed the Proposed l Standard Code for Concrete Reactor Vessels and Components ACI 359/ASME B&PV Code,Section III, Division 2. The ACI 359 code invoked rules and requirements consistent with the intent of Regulatory Guide 1.19. The intent being a uniform quality level consistent with the safety function of containment liners.
! The alternate requirements stipulated in Section
- 3.8.1.6.5 of the FSAR reflects those methods and I requirements performed in the construction of the CPSES l containment liners. These alternate methods and requirements were reviewed and found consistent with the l methods and requirements of CC-5500 of the ACI-359/ASME I B&PV Code, Section !!!, Division 2.
Therefore, the use of the proposed ACI-359/ASME code,
- with the alternate methods described in Section 3.8.1.6.5 l
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Attachment 1 to TXX-88040 January 15,~1988 Page 3 of 7 i FSAR Page -
(as amended) Description 1A(B)-8 Ccrrection: (Continued) of the FSAR, in lieu of Regulatory Guide 1.19 assures that the containment liner welds were performed and examined to a uniform quality level consistent with the safety function of containment liners.
lA B)-17 through Editorial: Remainder of section reissued due to 1A B)-80 shifts in the text.
1A(B)-18 Clarification: Clarifies the capabilities of the RMS monitors tu detect a 1 gpm RCS leak rate in less than one hour. Under conditions of high containment activities the RMS monitors may be unable to detect this leakage within one hour due to the masking effect of the background activity. Under these conditions grab samples of containment atmosphere will be obtained in accordance with the action statement of Technical Specification 3/4.4.6.1 for an inoperative Gaseous or Particulate Radioactive Monitoring System.
1A(B)-20 and Clarification: For Regulatory Guide 1.46, adds the word 1A(B)-21 "except" to clarify the type of discussion in Section 3.68.
, Revision: For Regulatory Guide 1.48, for ASME Code Class '
2 and 3 BOP valves, the current CPSES FSAR defines pressure limits, but does not explicitly define stress limits. The FSAR design commitments for ASME Code Class 2 and 3 B0P active valves are taken from Regulatory Position C.11 and C.12 of Regulatory Guide 1.43 dated May 1973. Regulatory Guide 1.48 requires that Class 2 and 3 active valves be limited to normal ASME code design stress limits unless their operability during and after the SSE has been demonstrated by testing. Therefore, when the active valves have satisfied operability test requirements as Guide position (prescribed as presentedby onNote pages 111-48-4 of theand Regulatory 1-48-5),
the use of higher design stress limits stated in Regulatory Guide 1.48 are allowed. The higher design stress limits are the same stress limits used for non-l active valves. Section 3.98.2.2 endorses testing of mechanical and structurally complex equipment to demonstrate operability during and after a postulated earthquake. Operability is demonstrated for ASME Code
! Class 2 and 3 active valves by mounting the valves, valve l body at design pressure and temperature, directly on the j shake table or by conducting static deflection tests.
I Section 3.98.3.1.1, Note 1, for Tables 3.98-5 and 3.9B-6
- causes confusion concerning the design requirements l
(stress limits) for active and inactive valves. The current FSAR position conservatively require's that 80P Class 2 and 3 active valves be limited to normal ASME l code design stress limits although active valve i
Attachment 1 to TXX-88040 January 15, 1988 Page 4 of 7 FSAR Page (as amended) Description 1A(B)-20 and Revision: (Continued) operability during and after the 1A(B)-21 earthquake has been demonstrated by tests. .The FSAR is more restrictive than Note 11 of Regulatory Guide 1.48 which allows the use of higher design stress limits (equal to inactive valve design values) if active valve operability is demonstrated for the earthquake.
This overly conservative position has resulted in unnecessary revisions to vendor stress reports and the implementation of plant design modifications.
The proposed changes to the FSAR discussion replace the previous discussion to Regulatory Guide 1.48. This position is adopted because 80P ASME Code Class 2 and 3 valves design stress limits are increased to Emergency and Faulted condition values provided by Standard Review Plan 3.9.3, Rev. 1, dated July 1981. The higher design stress limits exceed the design stress limits provided by Regulatory Guide 1.48 but provide alternate criteria consistent with the design criteria employed in NSSS Class 2 and 3 valves. Piping stress limits are in accordance with ASME code allowables and nut dictated by Regulatory Guide 1.48.
1A(B)-23thru Revision: Rearranges the exception paragraphs for 1A(B)-24 Section C.2.g, C.3.h, C.5 and C.6 of NRC Regulatory Guide 1.52.
Adds exception to part C.2.g, which notes that flow rates and pressure drops for ESF filtration units are not recorded or monitored by the control room. Alarm annunciators in the control room for units used for post-DBA are used to monitor design limits.
Adds exception to part C.3.h, water drains. Check valves are used in lieu of seals or traps. Demister compartments for two primary plant ventilation systems and hydrogen purge filtration systems are not provided with seals, traps or check valves. By-> ass through this is filtered before discharged through tie stack.
Clarifies parts C.5 and C.6. Adds the revision of NRC Regulatory Guide 1.52 for parts C.2.g and C.6.
1A(B)-25 See Justification for page 1A(H)-31.
to TXX-83040 January 15, 1988 Page 5 of 7 FSAR Page (as amended) Description 1A(B)-32 Correction: Reflects current design practice; utilizes Winter 1978 Addenda to the 1977 Edition of the ASME Boiler and Pressure Vessel Code, Appendix 0,Section III, Division 1 in lieu of Regulatory Guide 1.67. This is acceptable since the NRC withdrew Regulatory Guide 1.67 -
and-supported the aforementioned ASME document as having equivalent requirements.
1A(B)-36 Update: TV Electric Nuclear Operations does not intend on performing the pseudo rod drop, pseudo rod ejection and below bank rod teste referenced in Regulatory Guide 1.68, Revision 2, Appe.Jix A, Sections 4c, Se, Sf and 51.
The justification for not conducting these tests includes the following: Previous td ts on similar facilities indicates little new information is generated by the perfonnance of these tests. Recent industry experience indicates that there is increased potential for causing severe xenon transients by performing these tests. The duration and cost of the physics testing program are reduced by not performing these tests. In addition.
Westinghouse has indicated that performance of the 50'4 power pseudo dropped rod test could lead to a violation of the F-delta-H fechnical Specification.
1A(B)-45 Revision: The AC Essential Lighting System and DC Emergency Lighting Systerr. are being reclassified as non-Class 1E. Lighting is not a safety related function.
The AC Essential Lighting System is fed from safety related buses. It is isolated from the Class lE power sources with two separate Class 1E breakers connected in series. These breakers are coordinated with their supply breaker and will be tested periodically. The circuits are routed in conduit to provide physical and electrical independence beyond the isolation breaker. The conduit meets the separation criteria given in Section 8.3.1.4.
The DC Emergency Lighting, which was previously fed from Class 1E station batteries, will be fed from dedicated non-Class 1E batteries. These circuits are also routed in conduit to provide physical and electrical independence from Class 1E criteria given in Section 8.3.1.4.
Addition: Clarifies the separation requirements for fiber optic cables. As fiber optic cables carry no electrical energy by themselves, they are not required to maintain physical sep ration between non-Class 1E and Class 1E circuits.
Addition: Adds cross reference to the description in Section 7.1.2.2 for B0P Instrumentation Separation requirements.
Attachment 1 to TXX-88040 January 15, 1988 Page 6 of 7 FSAR Page (as amended) Description 1A(B)-45 and Revision: Add:s exception to Regulatory Guide 1.75 1A(B)-46 Regulatory Position C.1 for the non-Class 1E diesel generator neutral grounding transformer. This transformer i connected to the neutral of the Class 1E diesel generator. An analysis has been performed which demonstrates that a fault on the non-Class IE portion of the circuit will not cause an unacceptable influence on the Class 1E system.
1A(B)-48 Revision: Adds an exception to Regulatory Guide 1.75 Regulatory Position C.12 for listed components which are net high energy equipment but are located inside the Cable Spreading Room / Control Room complex and have power circuits routed in exclusive conduits within the Cable Spreading Room / Control Room complex.
lA(B)-61 See Justification for page 1A(N)-57 and 1A(N)-58.
lA(B)-71 Revision: CPSES will use IEEE Std. 450-1980 rather then the 1975 version for compliance with Regulatory Guide 1.129. 1EEE 450-1980 primarily revi:ed and clarified the methodology used to calculate the battery capacity for an -
acceptance or perfonnance test. Compliance with IEEE 450-1980 is acceptable provided that the method used to calculate battery capacity is consistent (i.e., use of the 1980 equation with the 1980 temperature correction or use of the 1975 equation with the 1975 temperature correction factors). Since the two methods are essentially equivalent, the intent of Regulatory Guide 1.129 is not.
1A(B)-72 and Revision: Revises commitment to Regulatory Guide 1.131 1A(B)-73 for Raychem Corp. Heat Shrinkable Field Splicing System for Class 1E Electric Cables (Type WCSF-H). Subject splices were flammability tested in accordance with IEEE Std 383-1974. Regulatory Guide 1.131 amends portions of this standard. The flame test conducted does not meet the requirements of the Regulatory Guide. The additional requirements of the Regulatory Guide do not jus'.ify replacing existing Raychem field splices which met the IEEE testing requirements.
IA(B)-76 and Revision: Adds exceptions to paragraph C.1.b, C.2.b 1A(B)-77 and C.2.c to imC Regulatory Guide 1.137. Clarifies the exceptions tc 5.1 and 7.5 of ANSI N-175 and co-relates with sections C.I.d and C.1.g of HRC Regu'otory Guide 1.137 to the numbered items. The changes to the numbered items are as follows:
. Attachment I to TAX-88040' January 15, 1988 Page 7 of 7 FSAR Page (as amended) Description 1A(B)-76 and 1. Venting components are not designed to safety class 1A(B)-77 3 (as identified in paragraph 7.1 of ANSI N195-1976), however they are seismically supported and the vent paths are missile protected.
2 & 3. Editorial changes.
- 4. ASTM 0975-74 is updated to ASTM 0975-81, which updates the fuel oil monitoring program to current standards. The revised testing will test the parameters which indicate degradation or contamination of fuel during transit. The tests are based on a surveillance program report developed by Kurt H. Strauss and docketed earlier for the McGuire Nuclear Plant (Docket Nos. 50-369 and 50-370) by letter to Mr. H. R. Denton from Mr. H. B. Tucker, dated November 18, 1983.
provirles the updated ASTM method for sampling of diesel generator fuel oil and is an acceptable alternate standard in the industry.
1
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--e--. ,-y- _ ,. - - r- . , - --m-r ., ,e ,__ ----... y
Attachment 2 to TXX-88040 January 15, 1988 Page 1 of 1 CPSES FSAR AMENDMENT 66 DETAILED DESCRIPTION FSAR Page (as amended) Description 2.2-12 Correction: This change corrects the value stated for the elevation difference between the control room air intakes and the circulating water chlorine storage location to provide consistancy with design documents.
2.3-14 Editorial: Deletes the redundant wind velocity information from Section 2.3.1.2.11 "Extreme Winds".
Wind loading is discussed in Section 3.3.1.1 "Design Wind velocity".
2.4-49 Clarification: Deleted "Under normal operating conditions, there will be no controlled release of water to Squaw Creek to Squaw Creek Reservoir" and inserted "Controlled releases from Squaw Creek Reservoir are provided to maintain the minimum flow rate in Squaw Creek as required by the Texas Department of Water Resources Permit Number CP-20". This permit requires that TV Electric release enough water flow from Squaw Creek Reservoir to maintain a minimum flow of 1.5 cfs at the Highway 144 crossing over Squaw Creek.
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Attachment 3 to TXX-88040 January 15, 1988 Page 1 of 14 CPSES FSAR AMENDMENT 66 DETAILED DESCRIPTION FSAR Page (as amended) Description Section 3.2 Editorial: This section.is being reissued in the computerized format.
3.2-1 Editorial: Adds the word "seismic" for clarification to emphasize the seismic requirements (aspects) of GDC 2, since GDC 2 addresses other phenomena.
Clarification: The reference to ASME B&PV Code is deleted since it does not "identify and classify" seismic components, structures and systems, it is a design, fabrication, examination, installation, etc., Code.
3.2-5 AdditIion: This change reflects the updates of the Seismic and Q-lists in the FSAR based on the system design parameters for Uninterruptible Power Supply (UPS)
Area Air-Conditioning System.
3.?-9 Clarification: Added "..as defined in ANSI N18.2[4]" to clarify the specific reference.
3.2-11 and Clarification: The section for Non-Nuclear Safety (NNS) 3.2-12 has been editorially updated to include a discussion on Class 5 and Class G designations and their relationship to Seismic Category 11 is described. This input reflects the current content of the latest revisions of Specifications MS-100 and MS-200.
Clarification: The heading "Other Classifications" was deleted because Class 5, Class G and RWMS are not safety "classifications." Rcther, RWMS is more closely counted as a subsection of 3.2.2, system Quality Group Classification.
3.2-12 Editorial: A section of the RWMS descriptions is being relocated as indicated within the section.
Table 3.2-3 See Justification for page 3.2-5.
(Sht. 5) l l
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Attachment 3 to TXX-88040 January 15, 1988 Page 2 of 14 FSAR Page (as amended) Description Section 3.3 Editorial: This section is being reissued in the computerized fonnat.
3.3-1 Revision: This change adds a gust factor for all seismic Category I yard tanks. The gust factor for seismic Category I yard tanks has changed from "1.1." to "1.3".
ASCE Paper 3269 requires higher gust factor for smaller structures.
3.3-7 Revision: A change to indicate that all seismic Category I structures are to have sufficient capacity to withstand the 360 mph tornado wind velocity uniformly applied.
This change is in response to question Q130.1.
Table 3.3-1 Editorial: This table is being reissued in the computerized format. .
(Sht. 1) Correction: Adds door F-4Fx to table. Fire hazard analysis requires additional 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> rated door in fuel building. Tornado design assumption requires this door to be in open position during normal plant operation.
The door is designed to close during a fire.
(Shts. I thru 4) Revision: Deletes doors E-3, S-10, S-23, S-288, S-36, S-36A, A-20, A-21, S-30A, S-31, S-32, S-34 and 51-12.
These doors were required to be open for tornado venting i thus their removal will not affect tornado venting. "
(Sht. 2) See Justification for Table 3.3-1 (Sht. 1).
(Sht.3) Revision: Deletes door S-24A from Table 3.3-1. Doors S-24 and S-24A are in the normal access route from the hot lab to the primary side of the plant. Currently, these two sets of doors are located such that S-24A ,
cannot open completely due to the interference from door S-24. Because door S-24 perfonns the same tornado ,
venting scheme functions as door S-24A, the removal of door S-24A will not degrade CPSES's ability to withstand tornado wind loadings.
Section 3.5 Editorial: This section is being reissued in the computerized format.
3.5-27 Revision: Defines ductility criteria for steel columns with a slenderness ratio greater than 20. The ductility ratio for steel columns with a slenderness ratio greater than 20 needs to be defined to determine the overall response Of structural barriers to missile impact. This change meets the intent of Appendix A of the Standard Review Plan Section 3.5.3. i
Attachment 3 to TXX-88040 January 15, 1988 Page 3 of 14
- FSAR Page (as amended) Description Table 3.68-1 Addition
- Adds note 3 reference to table.
(Shts. 4 and 5)-
(Sht. 5) Correction: Removes duplicated listing of line 6-AF-1-29-2002-3.
Correction: Removes line 3-AF-1-26-2002-3 from table since this portion of piping is not energized during normal plant conditions as defined in FSAR Section 3.6B.2.1.5.
(Shts. 5 and 11) Addition: This change adds two additional lines (6-AF 88-2002-3 and 2-CS-1-165-2501R-2) to high energy line table based upon the definition of high energy lines provided in Section 3.68.
(Sht.34) Revision: Revises the description of Note 3 on Sht. 34 to require high energy line break (HELB) consideration during emergency conditions only. Since the lines contain insufficient stored energy to warrant ilELB consideration during normal plant operating conditions.
Section 3.78 Editorial: This section is being reissued in the computerized format.
3.78-5 Revision: References the usage of ASME Code Case N-411 for the analysis of the primary system loop to determine seismic loads transmitted to the steam generator upper lateral and lower lateral restraints. The use of the Code Case N-411 damping values has been accepted for use on piping systems analyzed by the response spectrum method.
3.7B-6 Editorial: Changes to page 3.78-6 consists of corrections to reference the correct Table and reflecting that it is a table of "rock" characteristics and not
. "soil" characteristics.
l 3.78-13 Clarification: Revises the text to eliminate the first
, sentence which appeared to be a commitment regarding when dynamic analysis is used. This sentence was really intended to serve as an introduction to the subsequent description of how we use dynamic analyses.
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Attachment 3 to TXX-88040 January 15, 1988 Page 4 of 14 FSAR Page (as amended) Description 3.78-22 Revision: AE functions are now provided by TUGC0 (TV Electric) or its contractors.
3.78-24 Revision: Expands the commitment on limiting stresses to allow exceeding 90 percent of the yield strength of this material when allowed by the applicable Codes or Standards as committed to elsewhere within the FSAR.
This revision makes this portion of the text consistent with the specific stress limits provided elsewhere (e.g.,
Section 3.9) of the FSAR.
3.78-50 Addition: Identifies that the mode spacing is evaluated based upon the frequency of the lower mode. This is consistent with implementation procedures but was not previously identified in the FSAR in this discussion.
3.78-56 Editorial: Typographical error add Subscript "ST" to "C" (Cst).
3.78-69 and Revision: Equivalent Static 1.oad Method section is 3.7840 modified to incorporate those cases previously covered by Section 3.78.3.8.1.1. For piping systems with nominal pipe diameter greater than 2" but greater than 4", which were previously covered by 3.78.3.8.1.1, are now addressed in accordance with 3.98.2.2.
3.78-71 thru Revision: Simplified design method outline in FSAR 3.78-74 Section 3.7B.3.8.1.1 is deleted. Simplified design method is repetitive of Section 3.78.3.5 Equivalent Static Load Method since both methods are based on static seismic analysis.
Section 3.7B(A) Editorial: This section is being reissued in the computerized fonnat.
3.7B(A)-19 thru Addition: Adds descriptions for STRUDL-SW, SHELL-1, 3.7B(A)-21 TIMHIS6, SBitil. Updates section to include major ,
computer programs used by Stone and Webster Engineering Corporation as a result of design validation activities at CPSES.
3.7B(A)-24 Addition: Adds references to reflect changes made on pages 3.7B(A)-19 thru 3.7B(A)-21.
Table 3.7B(A)-1 Addition: Adds list of computer programs used by SWEC.
(Sht. 2) Updates the table containing list of computer programs to identify computer program used by SWEC during design validation activities at CPSES.
- - -m ,---
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to TXX-88040 January 15, 1988 Page 5 of 14 ,
FSAR Page (as amended) Description Table 3.9N-10 Revision: Adds relief valve to Table to show that it is (Sht. 1) required to provide overpressure protection to RCS penetration piping during containment isolation.
Table 3.9N-10 Clarification: Deletion of numerical prefix of valves to (Shts. I thru 6) show table applicability to Units 1 and 2. Also revised, as indicated, method of actuation to be cont,istent throughout the list (for example: check and relief valves are considered self-actuating).
Section 3.98 Editorial: This section is being reissued in the computerized fonnat.
3.98-1 Editorial: Replacing the word "shutdown" with "conditions" is consistent with accepted Regulatory Guidance and Standard Review Plan usage when specifying faulted or testing "conditions".
3.9B-15 Correction: Deletes 3.98.1.4.2d which addressed anchor bolts because it was inappropriately incorporated in response to NRC question 0112.13 which specified component bolting and did not question anchorage bolting (example: Hilti installations).
3.98-17 Clarification: The first paragraph is revised to clarify that CP"iS Dynamic Transient Response Testing commitment includes visual observations.
Revision: The second paragraph is replaced wtth a listing of systems to be tested and their corresponding transient test to be performed. This list expands the scope of testing as a result of support requalifications effort.
Clarification: The third paragraph is clarified to explicitly describe that locations with instrument measuring capability measure transient loads for later comparison with predicted values (calculated).
Refinement in test data obtained will provide improved ability to judge test and analyses results.
3.98-17 and Clarification: The end of the third paragraph is 3.98-18 clarified and reworded since the first sentence of the third paragraph now states that tested systems are visually observed and instrument measurements are made at some locations. The acceptance criteria basis is better defined to be consistent with the detail provided on scope of systems to be tested.
Attachment 3 to TXX-88040 January 15, 1988 Page 6 of 14 FSAR Page (as amended) Description 3.98-18 Clarification: The first paragraph of Section 3.98.2.1.3 is rewritten due to the vague commitments and discussion presented. Clarified description of the scope of the '
Steady State vibration tests by explicitly providing the commitment of steady state vibration tests and listing of systems that fall within the test commitment.
3.9B-19 and Clarification: Revises the second paragraph of Section 3.9B-20 3.98.2.1.3 to clarify that observed vibrations by qualified engineers are not measured. The only measurements recorded are by instrument measuring devices that determine loading at those locations vibrations are evaluated to be excessive. Resolutions listed for resolving excessive vibration problems we.e clarified to reflect ASME code allowables as acceptance criteria and the acceptability of rerouting piping (considered part of support system).
3.9B-20 Clarification: Clarifies the second paragraph in Section 3.98.2.1.4 to reflect repetition of testing to ensure that thermal and vibration movements satisfy acceptance criteria (ASME code stress and fatigue allowables).
3.98-21 Clarification: Revises the fourth paragraph in Section 3.98.2.1.7 to eliminate reference to "familiar with the systems to be tested" since any personnel participating in test are trained and familiarized with their scope of testing responsibility.
Clarification: Compares test results with "predicted" results as determined by piping stress analyses.
3.9B-27 Revision: Revises text to show the removal of table 3.98-6 and that inactive and active valves are provided with the same stress limits.
Revision: Changes the commitment for combining dynamic pipe loads for components (Table 3.98-1A). Previously, for equipment, all loads were combined by the most conservative method. The intent of this change is to allow the combination of peak dynamic responses using the Square Root of the Sums of the Squares (SRSS) method.
The specific loads involved are seismic loads and other dynamic loads such as steam or water hammer. This revised commitment is consistent with the methodology used for piping which is also consistent with NUREG 0484, Revision 1. Piping has obviously met conditions A and 8 of the referenced NVREG. The flVREG is not limited to piping, but covers all ASME components. Therefore, use of the NUREG methodology is appropriate for equipment with the same loads accepted by piping.
See Justification for pages l A(B)-20 and 1A(B)-21, (Regulatory Guide 1.48).
Attachment 3 to TXX-88040 January 15, 1938 Page 7 of 14 FSAR Page (as amended) Description 3.9B-31 Clarification: The sentences was improperly worded and has been reorganized to clarify its meaning. This is not a technical change.
Clarification: Revises the discussion to put the discussion on rigid and non-rigid valves in one test and to clarify item "1". Item 1 could have been interpreted as a commitment to design all valves as rigid but this item was intended to identify which criteria applies to rigid valves and to point out that most valves are designed to be rigid. Parts of the existing text was reformatted to be items 6 and 7.
3.98-34 Clarification: On item 5 the test are performed with the valve at "design" pressure and temperature and not "rated values." Operability for CPSES is adequately demonstrated by using design values. Testing at rated values would be over-conservative and was never intended.
3.98-37 Clarification: Adds the word "active" to clarify that operability is demonstrated for safety-related "active" valves as discussed in the prior test.
3.98-40 Editorial: Corrects Table references.
3.98-44 Revision: Adds item "h" to allow the use of AISC supplement in analyzing structural tubing. This change is made to refine the analysis of structural tubing utilized in instrument impulse tubing supports for ASME III Class 2 and 3 safety applications.
3.98-44 and Clarification: This change provides a clearer 3.98-46 description in reference to 10CFR50.55a which could cause confusion or misinterpretation. 10CFR50.55a provides requirements for the Edition and Addenda of ASME Section XI to be applied during inservice and preservice inspection. It is unnecessary and impractical to state a particular code year in the FSAR because the applicable Code year is established based upon issuance of the operating license and reestablished on a 10-year interval basis.
Table 3.98-1A Clarification: Lists other dynamic events (e.g.. steam (Sht. 1) or water hammer) separately since these dynamic loads are combined in a different manner. See FSAR Section 3.98.3.1.1.
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Attachment 3 to TXX-88040-January -15, - 1988 Page 8 of 14
, FSAR Page (as amended) Description (Sht. 2) . Revision: Revises Table notes to incorporate the position that BOP inactive components and. valve 3 utilize the loading combination specified for the applicable plant conditions. See Justification for pages'1A(B) ,
and1A(B)-21,(RegulatoryGuide1.48).
Clarification: Added nmote 5. See justification for Table 3.9B-1A (Sht. 1).
Table 3.98-5 Revision: Replaces FSAR Table with a new Table identical to Table 3.9N-8 used for NSSS Class 2 and 3 valves. All B0P Class 2 and 3 valves will be shown to meet this criteria. See Justification for pages 1A(B)-20 and 1A(B)-21, (Reg. Guide 1.48).
Table 3.9B-6 Revision: Removes Table since Table 3.98-5 provides
- design criteria for inactive and active valves.
Table 3.98-7 Revision: Revises Table to show the addition of (Shts. 2, 3, relief valves to Table 3.98-7 that provide overpressure 4 and 5) protection for the Demineralized Water System, the i Chilled Water System, the Service Water System, the Primary Plant Sampling System and the Component Cooling Water System piping.
See Justification for Table 3.98-8 (Sht. 1 and 3)
Table 3.98-8 Revision: Revises Table to reflect addition of relief (Shts. I and 3) valves to Service Water and Component Cooling Water Systems to prevent the potential for overpressurization.
(Sht. 5) Revision: Revises Table to delete reference to main steam isolation bypass valves. This revision is part of l our response to NRC request for additional information i dated February 27, 1986, which was transmitted by our letter TXX-6126 dated December 8,1986.
! (Sht. 6) Revision: Revises Table to show Safeguards Building sump pumps as active components. This classification is
! consistent with design basis requirement that these sump pumps function to handle specific leakage rates without flooding of adjacent areas.
Table 3.98-10 Editorial: This table is being reissued in the l; computerized format.
(Sht.1) Revision: Revises Table to delete HV-23338, HV-23348, i HV-23358 and HV-23368. This revision is part of our
, response to NRC request for additional information dated l February 27, 1986, which was transmitted by our letter l TXX-6126 dated December 8,1986.
Clarification: Clarifies steam generator PORV (atmospheric dump) function (typical four places).
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Attachment 3 to-TXX-88040 January 15, 1988-Page'9 of 14 FSAR Page (as amended) Description Table 3.9B-10 Clarification: Method of actuation deignated for check (Shts. 2 thru 5, and relief valves previously designated as "
-7, 11, 12, 13 and changedtoshowthattheyare"self-actuatin/_\P"areg."
14 thru 16)-
(Shts. 2 thru 9, Clarification: Eliminates of Unit I numerical prefix to 11, 12, 13 and valve tag numbers, since this table listing is applicable 14 thru 17) to Units 1 and 2.
(Shts. 2, 5, Editorial: Deletes duplicated valve listings, corrected 9, 11 and 12) valve tag numbering errors and reinserted valves mistakenly removed.
(Sht. 5) Correction: Eliminates four non-nuclear safety valves that did not satisfy the prerequisites for being listed as active valves consistent with the requirements of FSAR Section 3.98.3.
(Sht. 11) Revision: Provides alternate method of actuation for valves LV-4500 and LV-4501 in the event instrument air supply is lost.
(Sht. 11A) Revision: Adds 4 valves to Component Cooling Water System which are active and provide cooling water to control room air conditioning.
(Shts. 12 and 16) Correction: Corrects indicated normal position for valves to open based upon flow diagrams and design basis documents.
(Sht. 13A) Revision: Adds 8 valves with in the Diesel Generator Fuel Oil System defined as starting air pressure boundary self-actuated active check.
(Sht. 14) Revision: Revises table to incorporate relief valve PS-193 to Process Sampling Primary Plant System. Relief valve provides protection from over pressurization during Containment Isolation.
(Shts. 13, 15 Correction: Corrects valves system designation based and 16) on flow diagrams and design basis documents.
(Sht. 17) Clarification: Adds two non-technical table notes.
Section 3.10B Editorial: This section is being reissued in the computerized format.
, 3.108-1 Revision: Reclassifies AC Essential Lighting System and DC Emergency Lighting System as non-Class 1E. (See Justification for page 1A(B)-45).
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to TXX-88040 January 15, 1988 Page 10 of 14 FSAR Page (as amended) Description 3.'10-7 Clarification: Clarifies that fact that "g" peak is not always used. Using the "g" peak'is merely a simplified and conservative approach to the design problem. Using the frequency analysis approach is more complex and more realistic. It is prudent to use the frequency analysis method at this time in lieu of modifying otherwise acceptable designs. The frequency analysis a3proach has been previously discussed in other parts.of t1e section (3.108.3).
3.11B-1 Clarification: Adds abnormal conditions.
3.118-2 Revision: Defines potentially harsh and mild environment areas at CPSES.
3.118-3 Clarification: Describes how flooding due to a DBA or a MELB is addressed. In TXX-6884, MELB's had previously been included with DBA's. HELB's (and the ,stential flooding that can result) is addressed by the CPSES System Interaction Program (See FSAR Section 3.6). '
Flooding due to a DBA is addressed by the Environmental Qualification Program.
Revision: Identifies Environmental Equipment Qualification Summary Packages to reflect current CPSES file designation.
Revision: Inserts "a potentially harsh environments" "
as appropriate for program consistency with the definition of mild environment areas.
3.118-4 Revision: Deletes reference to Table 3.118-5 which has been incorporated into the Appendix 3A, Table 4-1. A separate description of HELB is not required as it has .
been-incorporated with the rest of the environmental qualification program.
3.118-5 Editorial: TUGC0 changed to TV Electric.
Revision: Updates the discussion on qualified life to address EEQSP's.
3.118-5 thru Revision: Revise table refersaces to new consolidated 3.118-7,11 and Appendix 3A, Table 4-1.
3.118-13 3.11B-6 Editorial: Corrected typographical error from Category "1" to Category "I". Non-technical change.
3.118-7 Clarification: Reworded paragraph to clarify Accident Monitoring equipment environmental qualification requirements.
Attachment 3 to TXX-88040 January 15, 1988 Page 11 of 14 FSAR Page (as amended) Description 3.11B-8 and Revision: Describes qualification program as applied to 3.118-9 Class 1E equipment' located in a mild environment area.
3.118-9 Addition: Adds a reference to Regulatory Guide 1.100.
This addition is consistent with revised description of Class 1E equipment located in a mi'd environment area.
Revision: Inserts "in a potentially harsh environments" as eppropriate for program consistency with the definition of mild environment areas.
Revision: Adds a reference to the Environmental Equipment Qualification Summary Packages which identifies ;
these results and analysis. This information is removed from current FSAR Tables.
3.118-10 and Clarification: Equipment which is not code safety-3.118-11 related ventilation is qualified for the environment .
that results from the loss of ventilation due to a LOCA with loss of offsite power.
3.118-12 Revision: Lower limit operating temperatures, relative humidity and operating pressures modified to reflect plant service conditions.
3.118-13 Revision: Inserts "in a potentially harsh environment (i.e., inside containment)" for program consistency with the definition of mild areas category.
Revision: Section rewritten to reflect revised plant service conditions for chemical environment. .
Addition: Reference to updated Westinghouse Radiation Analysis manual incorporated.
Revision: Deletes the statement that the radiation calculations did not take credit for containment spray or plate out. Radioactivity removal by containment spray and plate out was included as allowed by NUREG-0588.
3.118-15 Addition: See Justification for page 3.118-9.
Table 3. lib-2 Revision: Deletes Table 3.118-2 because infonnation is provided in Section 9.4.
Table 3.118-4 Revision: Deletes Table 3.118-4. Active values are discussed in Section 3.0 and 6.2. The environmental parameters have been consolidated in appendix 3A, Table 4-1.
Table 3.11r.; Revision: Tables deleted and data consolidated in Appendix 3A, Table 4-1. ,
Attachment 3.to TXX-88040 January 15, 1988 Page 12 of 14 FSAR Page (as amended) Description Appendix 3A Addition: References summary data for Class 1E equipment 1-1 located in a potentially harsh environment in Table 4-1.
Revision: Changed "equipment" to "systems" to be consistent with Section 7.4.
1-1 and Revision: Defines mild environment areas at CPSES.
1-la Appendix 3A Revision: Adds reference to the EEQSP's.
1-lb 1-lb and 1-Ic Revision: Describes qualification program as applied to Class 1E equipment located in a mild environment area.
1-Ic Revision: See 3.118-7.
2-1 Revision: Deleted historical reference to the original AE and replace with TV Electric.
Update: Summarizes the scope of the consolidated 80P and NSSS programs instead of addressing the B0P scope alone.
2-3 Revision: Deleted discussion concerning deleted Parts (Section) 4.0, 6.0 and 7.0.
Revision: Adds specific reference to the Environmental Equipment Qualification Suninary Packages.
Revision: Deleted reference to the environmental qualification data previously described in Tables 5-1 and 5-2. (See Justification for Section 3.11, Appendix 3A, Part 5.0.) >
Revision: Defines the difference in application for potentially harsh and mild environments. ,
3-1 Clarification: Sentence added to clarify scope of
, environmental qualification program for equipment located l in a mild environment.
Appendix 3A Table 3-1 Clarification: Provides additional information on the (Shts. 1, 4, 5, assumptions used to calculate, model and develop various 8 thru 15) profiles which affect equipment qualification (i.e.
radiation, temperature and pressure).
(Sht.22) Clarification: See Justification for page 3.118-3 (clarification on flooding).
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Attachment 3 to TXX-88040 January 15, 1988 A Page 13 of 14 FSAR Fage' .
Description (as 6.nended) 1 Table 3-1 Revision: Adds that Cesium-137 is used as a radiation (Sht.25) source for environmental equipment qualification. The use of Cesium-137 has been accepted by the NRC in Reg.
Guide 1.89, Rev. 1.
(Sht.30) Revision: 100C rule is not used for environmental equipment qualification and was therefore deleted from this section.
(Sht.33) Clarification: Provides a clear statement that the CPSES documentation complies with the requireWnts of IEEE Std.
Appendix 3A Table 3-2 Clarification: Deletes the generic Westinghouse response (Sht . 21 thru 24) and refers to fable 3-1 where a CPSES plant specific response is provided. .
(Sht 28) Revision: Deletes statement regarding equipment being !
located above the flood level and refer to Table 3-1 which refers to the FSAR text. i (Shts. 36 and 37) Revision: Updates the description of qualification methods by referencint Table 3-1.
(Shts.37and38) Revision: Deletes the discussion on the relationship between the generic program and the CPSES plant specific parameters.
(Sht.46) Editorial: Deletes the updated phrase "the use of materials and components."
l l Section 3.11, Revision: Deletes the equipment qualification status Appendix 3A, list provided in the prior Amendment Section 4.0. All Part 4.0 equipment will be qualified prior to fuel load and status (Sht.4-1) maintenance in the Equipment Qualification documentation at CPSES.
l Table 4-1 See Justification for Section 3.11, Appendix 3A, Part (Shts. I thru 5.0.
36) i Section 3.11, Revision: Replaces Tables 5-1 and 5-2 with a revised Appendix 3A, consolidated Table 4-1. This table incorporates l Part 5.0 information previously provided in several different (Sht. 5-1) tables of the FSAR. The table retains the basic format used in the deleted Tables 5-1 and 5-2 but presents the postulated design information only. The results are located in the Environmental Equipment Qualification Summary Packages at CPSES.
Attachment 3 to TXX-88040 January 15, 1988 rage 14 of 14 FSAR Page (as amended) Description Section 3.11, Revision: Parts 6.0 and 7.0 of Appendix 3A have Appendix 3A, ~been deleted. These sections previously described the Parts 6.0 and the procedures used to perform environmental 7.0 qualif kation reviews and acceptance. The procedures (Shts. 6-1 and used in environmental qualification are available on j 7-1) site, t
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4 J
b 4
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.h Attachment 4 to'TXX-88040
- d. January 15, 1988 y . Page 1 of 1 ll CPSES FSAR AMENDMENT 66 DETAILED DESCRIPTION FSAR Page (as amended) Description Section 4.2 Editorial: This section.is being reissued in the
, computerized format.
4.2-60 Clarification: Changes this paragraph to agree with FSAR Table 14.2-3, the initial start-up test summary entitled "Rod Drop Tests." Also provides agreement with the method described in Reg. Guide 1.68, Rev. 2, Appendix A, paragraph 2.b.
Section 4.4 Editorial: This section is being reissued in the computerized format.
4.4-55 Correction: Updates FSAR to reflect current testing methodology for obtaining reactor coolant flow measurement. Replaces discussion of loop 3ressure drop ,
data and coolant pump performance data wit 1 a discussior.
based on differential pressure data. ,
4.4-59 Clarification: Provide clear description of Loose Parts ,
Monitoring System installation at CPSES. The system is !
installed non safety-related (non seismic).- ,
The SER (Section 5.4.5) implied that the system design complies with Reg. Guide 1.133 (based on TV Flectric letterTXX-3321). The scope of this letter was limited to the vendor's design.
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JAttachment 5 to TXX-88040 s January 15, 1988
'Page 1 of 3 CPSES FSAR AMENDMENT 66 ,
OETAILEO DESCRIPTION FSAR Page
- (as amended) Description
, 5.1-9 Revision: -Deletes reference to sheet 3 of Figure 5.1-1.
- This sheet duplicates information 61 ready contained in sheet 2.
1 Figure 5.1-1 Revision: Deletes sheet 3. This sheet duplicates informatior, already contained in sheet 2.
5.2-13 Revision: Revises the temperature at which power lockout of the accumulator isolation valves and the non-operating ;
charging must be performed. The temperature was rc<ised '
from 425 degrees to 350 degrees to be consistent with the Technical Specification requirement that both Trains of-pumps must be operable in Mode 3. The SER indicates that .
the accumulators and the charging pumps not required to ,
be operable are locked out at 4250F, The SER will -
require revision as a result of this change.
I Correction: . Adds the word "preferred" with reference to the mode of operation for the performance testing of ECCS pumps. This is to allow testing during cold shutdownd which is specifically required by the Technical Specifications.
Clarification: Identifies more clearly the conditions under which cold shutdown testing of the ECCS pumps can occur.
5.2-31 and See Justification for page 3.98-44.
5.2-35 5.2-37 See Justification for page 3.9B-44.
5.2-39 Editorial: Deletes the sentence which states that additional descri) tion of the Leakage Detection System can be found in t1e Technical Specifications. This sentence is deleted because a detailed description of the
- Leakage Detection System is already contained in this ,
! FSAR Section. Referencing the Tee.hnical Specifications [
for the description is inappropriate, t i
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Attachment 5 to TXX-88040 January 15, 1988 Page 2 of 3 FSAR Page hsamended) Description Table 5.2-2 Editorial: Table 5.2-2 is being reissued with new format (Shts. I thru 4) for change bars, sheets renumbered and typographical errors corrected. ;
(Sht.2) Revision: This change revised the Steam Generator and Pressurizer primary manway closure hardware from bolts to studs, washers and nuts. '
(Sht.3) Revision: Deletes reference to the RTO bypass loops.
The bypass loops were capped as a result of a modification to install N-16 power monitors (for flow measurements) and cold leg RTO Thennowells (for temperature measurement).
Table 5.2-5 Revision: This change revises the Reactor Coolant Water (Shts. I and 2) Chemistry specifications for pH, hydrogen, total suspended solids, and boric acid, to be consistent with Westinghouse Project Specifications", Revision 4.
5.4-21 See Justification for page 3.98-44.
5.4-44 Correction: Deletes reference to the Boron Injection '
Tank (BIT). The removal of the BIT was described in a previous amendment. This reference was inadvertantly retained.
Revision: Adds statement that hot leg bypass connections dre plugged and not used. (See Justification for Table !
5.2-2, sheet 3).
5.4-45 Revision: Describes the functional removal and capping of the RTO bypass maniiold connections.
Revision: Deletes item 7 which refers to the RTO Hot leg Bypass Piping.
5.4 46 Editorial: Renumbers remaining items because of the deletion of item 7.
Revision: Adds (to the revised item 9) a statement that the hot leg bypass scoop element is plugged and not used. '
1 i
Attachment 5 to TXX-88040 January 15, 1988 Page 3 of 3 FSAR Page :
(as amended) Description '
5.4-48 Revision: Deletes reference to loop bypass lines. ,
5.4-88 Revision: Adds a description of the RCS Loop Pile restraints which are functionally removed from t1e CPSES
-Unit 1 and 2 design by the removal of saddle blocks and shims. Additionally, the lateral restraints and non- :
, crushable insulation, although not required, are to remain as installed.
1~ r 1
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Attachment 6 to TXX-88040
'Janua ry J 3, 1988 Page 1 of 15 CPSES FSAR AMENDMENT 66 ,
DETAILED DESCRIPTION FSAR Page >
(as amended) Description Table 6.18-1 Editorial: This table is being reissued in the computerized format.
(Sht. 2) Correction: Provides correct material for ESF piping.
6.2-79 Revisicn: Deletes the requirement to check leakages for relief valves located inside containment. This is consistent with Note 5 of Table 6.2.4-2 which is arplied to items 33 and 34. Containment pressure will cause any .
relief valve leakage to be reduced.
6.2-82 Addition: Provides a paragraph on the SIS test line pressure indicator to describe the use of a pressure indicator as a containment isolation boundary. The SER, in Section 6.2.3, states "containment penetrations whose isolation provisions do not satisfy the explicit requirements of the GDC (55 or 56 as appropriate) but which are acceptable under some other defined basis.....are discussed below." The use of a pressure i
- indicator as a containment isolation boundary does not satisfy the explicit requirements of the GDC but is acceptable on the basis provided in this amendment. The SER may require revision to include a discussion of this additional penetration exception, t
6.2-82 Addition: Adds a description of the special measures taken to ensure that local vent, drain and test connection valves, which are located within the containment isolation boundary, provide containment integrity. Although these valves function as containment ,
1 isolation valves, they are excluded from the isolation valve list because of the special measures taken.
4 1
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Attachment 6 to TXX-88040 January 15, 1988 Page 2 of 15 FSAR Page (as amended) Description 6.2-83 Revision: Adds item 10 under "Special Containment Isolation Provisions". This item describes the use of thermal relief valves to protect isolated and stagnant fluid penetrations which may be subject to external heat sources. Since the isolated fluid is between containment isolation valves, the thermal relief valve becomes a containment isolation valve. NUREG-0800, Section 6.2.4, 11.6.g allows the use of relief valves as containment isolation valves, provided the set pressure is than 1.5 times the containment design pressure. greater 6.2-101 Revision: Deletes reference to calculation of the dose at the exclusion area boundary for containment hydrogen purging because the dose is no longer calculated.
(See Justification to page 15.6-40) 6.2-103 Correction: Provides correct reference to surface area and weight tables for aluminum and zinc.
6.2-104 Revision: kevises total hydrogen within primary coolant system from 1191 scf to 1701 scf. Also revises maxinum cmg/kg.hy rogen These concentration changes were made in
'.ethe be RCS consistent from 35 withcm3/kg to 50 Westinghouse Chemistry Criteria and Specification 6.2-106 Correction: Corrects flow rate of hydrogen produced by Corros500.
6.2-110 Revision: Based on the post-LOCA hydrogen production rate the actual time to 3's hydrogen concentration is 12 days. The previously stated 14 days was approximate and is revised.
Clarification: Changes "Hydrogen Purge air filtration units" to "Hydrogen Purge exhaust filtration units".
Clarification: Expands the description of the ANS Safety class 2 "equipment" to include only the containment isolation valves, the piping between them, and the piping inside containment.
Clarification: Changes "beyond the isolation valves" to "bevond the outboard containment isolation valves".
6.2-118 Revision: See Justification for page 6.2-104 Clarification: Deletes statement "during steady state plant operations above IMW power level." Westinghouse Chemistry criteria and Specifications do not inciude this l condition.
. - _ _ _ _ _ _ _ - _ _ _ . to TXX-88040 January 15, 1988 Page 3 of 15 FSAR Page (as amended) Description 6.2-128 Revision: Rev'ses the text to allow performance of either a reduceJ or full pressure periodic Type A (ILRT) test. Periodic tests (Reduced and Full) and associat.ed supplemental test acceptance criteria are also provided consistent with the requirements of 10CFR50 Appendix J.
Revision: Adds clarification to differentiate the addition of local leakage rate results to the Type A test upper confidence limit (UCL) in the preoperational and periodic tests. The practice used in the Unit 1 preoperational test as allowed by ANS/ ANSI 56.8-1981 Section 3.2.1.4 involved isolating problem penetrations during the Type A test, then adding their post repair Type B or C results to the Type A VCL. IE Information Notice 85-71, "Containment Integrated leak Rate Tests" was issued to define minimum pathway leakage and discuss methods acceptable to NRC Staff for establishing an "as found" Type A test leakage rate based on pre-test Type B&C repairs. Type A test leakage corrections for penetrations isolated during the performance of the Type A test were subsequently addressed in the draft regulator HS 021-5)y This guidedraft endorsement regulatoryofguide ANSIprovided
/ANS 56.8-1981 (Task supplementary guidelines for the correction of the UCL (At!SI/ANS 56.8-1981 Section 3.2.6) using minimum pathway leakage for penetrations isolated during the Type A test.
Therefore the FSAR change differentiates between preoperational and periodic test in this regard.
Periodic tests use minimum pathway leakage rates determined by Type 8 or Type C testing of isolated penetrations.
Clarification: Provides more detail for penetrations that are water filled during the perfermance of the type A test. Table 6.2.4-4 lists penetrations which are water filled during type A testing. These fluid lines are part of systems that during post-accident recovery are operated at a pressure significantly higher than containment pressure, or are required for safe and efficient conduct of the test, or are lines designed in accordance with Regulatory Guide 1.11. Table 6.2.4-4 does not list all penetrations that are not drained and vented. Specifically, for GDC 57 penetrations / valve arrangements the piping system inside containment is not directly open to the atmosphere during normal and aost-accident conditions. The status of fluid within tie piping (drained /not drained) is not relevant to the Type A test for these closed systems. This satisfies the 10CFR50 Appendix J exemptions to venting / draining provisions (para, III 9.1.d).
b Attachment 6 to TXX-88040 January 15, 1988
-Page 4 of 15 FSAR Page (as amended) Description 6.2-130 Revision: Adds peak pressure leakage rate criteria (See Justification for page 6.2-128) ;
Clarification: Clarifles acceptance criteria for supplemental tests.
6.2-132 Revision: Adds discussion on minimum pathway local leakage rate values for periodic tests (See Justification for page 6.1-128). .
Clarification: The personnel and emergency airlock gasket testing arrangement is shown in FSAR Figure 3.8-21 as a dogtooth cross section vice a double (dual) gasket arrangement. The equipment hatch and fuel transfer tube penetrations employ a double (dual) gasket arrangement.
Section 6.2.6.2 is revised as noted to provide a generic description of the seal testing arrangements.
6.2-134 Clarification: Deletes statement which indicates that the valve isolation tanks are to be leakrate tested. The requirement to leakrate test these tanks was previously deleted in Amendment 38 as discussed in FSAR Section 6.2.4.1.3. The deletion of this requirement was approved in SSER 6. This revision makes this Section consistent with Section 6.2.4.1.3.
- Addition: The addition of Part 4 to Section 6.2.6.2 provides a description of maintenence and containment leak rate test pressurization / pressure sensing penetrations that are Type B tested. Reference FSAR Table 6.2.4-2 for specific testing commitments. FSAR Figure 9.4-6, Drawing BRP-PN-1-RB-001 and Drawing BRP-PN-1-RB-002 detail specific testing arrangements. With the addition of Part 4, all penetrations that are Type B '
tested as discussed in Section 6.2.6.2. '
6.2-137 Correction: This change corrects the title to ANSI /ANS 56.8-1981.
Table 6.2.2-4 Correction: This change revises the material used for the Containment Spray System eductors.
Table 6.2.4-1 Editorial: This table is being reissued in the computerized format. :
(Sht. I and 1A) Revision: Adds items Sa, 5b, 9a, 9b, 13a, and 13b.
These are existing valves that were inadvertently omitted from this table.
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Attachment 6 to TXX-88040 January 15, 1988 7 Page 5 of 15 -
FSAR Page (as amended) Description Table 6.2.4-1 Revision: Adds items 18a and 18b.
These are existing *
(Sht.2) valves inadvertently omitted from this table.
Editorial: The feedwater Tempering Line is renaaed the Feedwater Preheater Bypass Line. ,
Revision: Deletes items 20b and 22b. The Feedwater Bypass Header Drain Isolation valves have been functionally removed by capping off the piping downstream of the valves. Renames remaining c, d, e items to be b, c and d.
(Sht.3) Editorial: Renames the Feedwater Tempering Line.
i Revision: Deletes items 24b and 26b (See Justification forTable6.2.4-1,Sht.2, Revision). ,
(Sht.4) Revision: Adds item 41a. This is a thermal relief valve as described in page 6.2-70 above.
(Sht. 5) Revision: Adds item 52a. This is a thermal relief valve.
Editorial: Changes "air *" to "water".
(Sht. 6) Revision: Adds items 60a and 61a. These are thermal relief valves.
Editorial: Changes "air *" to "water".
Correction: Revises applicable GDC from 56 to 55 in item 63.
Addition: Adds FSAR figure number to item 70.
Correction: Corrects line size in item 71. .
Addition: Adds new items 74a, 77a, 78e, 80a, 81, and i (Sht. 7) 83a. These are thermal relief valves. -
Correction: Revises isolation valving arrangement number !
and FSAR figure number in item 81. ,
Correction: Corrects line size in item 81. ;
, Addition: Adds figure number to item 84. :
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Attachment 6 to TXX-88040 January 15, 1988 Page 6 of 15 FSAR Page (as amended) Description Table 6.2.4-1 Correction: Revises sensor designators for items 92, 95, '
(Sht 8) 98 and 101.
Addition: Adds figure numbers to items 97 and 100.
(Sht.9) Revision: Adds items ll4a and 120a. These are thermal relief valves.
Correction: P.evises line sizes in items 111, 112, 114, 116 and 118.
Addition: Provides the appropriate figure number for item 115.
Correction: Corrects line size in item 116.
(Sht. 10) Revision: Adds item 121a. This is a thermal relief valve.
Correction: Revises line size in item 123.
Addition: Provides the appropriate figure number for item 124.
Table 6.2.4-2 Editorial: This table is being reis:ued in the computerized format.
(Sht. 1 and 1A) Revision: Adds "Note 8" to the Table title. This note states that vent and drain valves and test connections located within the containment penetration boundary are not listed in this table. However, they meet all the requirements of containment isolation valves.
Revision: Adds items Sa, 5b, 9a, 9b, 13a and 13b. These are existing containment isolation valves which were inadvertently omitted from this table.
Revision: Revises items 2, 7, 11 and 15 to change the primary method of valve actuation f rom "manual" to "local manual". The revision is part of our response to the NRC request for additional information dated February 27, 1986 which was transmitted by our letter TXX-6126 dated December 8, 1986 Revision: Adds items 18a and 18b. These are existing containment isolation valves which were inadvertently omitted from this table.
(Sht. 2) Revision: Deletes items 20b and 22b (See Justification for Table 6.2.4-1, Sht. 2, Revision).
Attachment 6 to TXX-88040 January 15, 1988 Page 7 of 15 FSAR Page (as amended) Description Table 6.2.4-2 (Sht. 3) Revision: Deletes items 24b and 26b (See Justification l for Table 6.2.4-1, Sht. 2, Revision). l (Sht. 4) Revision: Adds item 41a. This is a thermal relief valve as previously described.
(Sht. 5) Revision: Adds item 52a. This is a thermal relief valve '
- as previously described.
(Sht. 6) Revision: Adds items 60a and 61a. These are thermal relief valves as previously described.
(Sht. 7) Revision: Adds items 77a, 78a, and 80a. These are l thermal relief valves. '
(Sht. 8) See Justification for Table 6.2.4-2 (Sheets 1 and la), !
"Revision: Adds ' Note 8' to the table title."
(Sht.8A) Revision: Adds item 114a. This is a thermal relief i valve. !
(Sht. 9) Revision: Adds items 1, 120a and 121a. These are thermal relief valves as previously described.
i (Sht. 10) Revision: Adds a description of Note 8.
Table 6.2.4-3 Editorial: This table is being reissued in the -
computerized format. -
(Shts.Iand1A) Correction: Deletes reference to steam line isolation signal in items 2, 7, 11 and 15. These are manual valves.
l Revision: Adds applicable power supply Train to power operated valves previously omitted from this table.
- Revision: Adds items Sa, 5b, 9a, 9b, 13a and 13b. These are isolation valves previously omitted.
Revision: This change revises items 2, 7, 11 and 15 to delete the containment isolation signal referenced for '
the main steam isolation bypass valves. This revision is ;
i, part of our response to the NRC request for additional -
- infonnation dated February 27, 1986 which was transmitted ,
- by our letter TXX-6126 dated December 8, 1986, t
(Shts. 2 thru 13) Revision: Adds applicable power supply train to power ,
j operated valves previously omitted from this table.
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Attachment 6 to TXX-88040 January 15, 1988 i Page 8 of 15 :
FSAR Page (as amended) Description Table 6.2.4-3 (Sht. 2) Revision: Adds items 18a and 18b. These are isolation valves previously omitted. 1 Correction: Valve power failure mode for items 19 and ;
20a is revised to Fail-As-Is (FAI).
Revision: Deletes item 20b (See Justification for Table 6.2.4-1, Sht. 2, Revision). j (Sht.3) Correction: Valve power failure mode for items 21, 22a !
and 23 is revised to Fail-As-Is (FAI).
4 Revision: Deletes item 22b (See Justification for Table f 6.2.4-1, Sht. 2, Revision). !
(Sht. 4) Correction: Valve power failure mode for items 24a, 25 l and 26a is revised to Fall-As-Is (FAI). -
Revision: Deletes items 24b and 26b (See Justification i
for Table 6.2.4-1, Sht. 2, Revision).
(Sht.6) Revision: Adds item 41a. This is a thermal relief valve l as previously described.
[
(Sht. 7) Revision: Adds item 52a. This is a thermal relief valve as previously described.
(Sht.8) Revision: Adds items 60a and 61a. These are a thermal r relief valves as previously described.
(Sht. 9) Revision: Adds items 74a, 77a and 78a. These are !
i thennal relief valves, f
(Sht. 10) Addition: Adds items 80a, 81a and 83a. These are !
thermal relief valves. !
(Sht. 11) Revision: Adds applicable power supply Train to power operated valves previously omitted from this table.
l (Sht.12) Correction: Adds valve closure times in item 109 i (previously listed as N/A).
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. Attachment 6 to TXX-88040
. January 15, 1988~- !
Page 9 of 15 FSAR Page-(asamended) Description Table 6.2.4-3 i
-(Sht. 13) Correction: Adds valve closure times in item 110
- (previously listed as N/A).
Revision: Adds items ll4a and 120a. These are thermal relief valves as previously described.
(Sht.14) Revision: Adds item 121a. This is a thermal relief valve.
Table 6.2.4-4 Revision: Deletes items 51, 111 and 112.
Items 111 & 112 are deleted because they are GDC 57 i penetrations not required to be listed per discussion on t page 6.2-127. Note is added for clarification.
Item 51, penetration MIII-11 is deleted from the Table.
This is consistent with Rev. 3 of the Westinghouse Precautions, Limitations and Setpoints (TBX-490) and the following cold shutdown operating procedures: IP0-001A' "Plant Shutdown from llot Standby to Cold Shutdown", 50P- -
103A "Chemical & Volume Control System" and S0P-108A *
"Reactor Coolant Pump. This penetration (Seal Water i
- Return and Excess Letdown) will be drained or vented
- during the Type A test, and another penetration will be used to accomplish its function. .
Table 6.2.4-5 Editorial: This table is being reissued in the .
l computerized format.
(Shts. I and 1A) Revision: Adds items Sa, 5b, 9a, 9b, 13a, 13b, 18a and 18b. 1hese are containment isolation valves that had been inadvertently omitted from this table. ;
l Addition: Adds new test connection and references to note 13, 17 item 20a. ,
(Sht. 2) Revision: Deletes items 20b, 22b and 24b (See >
Justification for Table 6.2.4-1, Sht. 2, Revision),
i l (Sht. 3) Revision: Deletes item 26b (See Justification for Table 6.2.4-1, Sht. 2, Revision). ;
' (Sht. 5) Revision: Adds item 41a. This is a thermal relief valve as previously described.
~
(Sht. 6a) Revision: Adds item 52a. This is a thennal relief valve I as previously described. 7 i
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to TXX-88040 January 15, 1988 Page 10 of 15 FSAR Page (as amended) Description Table 6.2.4-5 (Sht.8) Revision: Adds item 60a and 61a. These are thermal relief valves as previously described.
(Sht. 9) Revision: Adds item 74a. This is a thermal relief valve as previously described.
(Sht. 10 and 10A) Revision: Adds items 77a, 78a and 80a. These are thermal relief valves as previously described.
Addition: Adds new test vent to item 80 and references Note 13.
(Sht. 11) Revision: Corrects an existing test vent and adds two '
new test vents to item 83.
(Sht. 13) Revision: Adds item 114a. This is a thermal relief valve as previously described.
Correction: Corrects two test connections in item 113.
Correction: Moves reference to IRC-005 and Note 13 from the test vent column to the test connection column.
Correction: Corrects block valve column in item 116.
(Sht. 14) Revision: Adds items 120a and 121a. These are thermal relief valves as previously described.
Table 6.2.4-6 (Sht. I and 1A) Revision: Adds items Sa, Sb, 9a, 9b, 13a and 13b. These are containment isolation valves that had been inadvertently omitted from this table.
Revision: Changes classification of items 5, 9 and 13 from "non-essential" to "essential" and changes Post-accident function to "Atmospheric Relief".
(Sht. 2) Revision: Adds items 18a and 18b. These are containment isolation valves that had been inadvertently omitted from this table.
Revision: Changes classification of items 18 from "non-essential" to "essential" and "Post-accident safety function to "Atmospheric Relief".
to TXX-88040 January 15, 1988 Page 11 of 15 FSAR Page (as amended) Description Table 6.2.4-6 (Sht. 2) Revision: Deletes item 20b (See Justification for Table 6.2.4 1, 5ht. 2, Revision).
(Sht.3) Revision: Deletes item 22b (See Justification for Table 6.2.4-1, Sht. 2, Revision).
(Sht. 4) Revision: Deletes items 24b and 26b (See Justification for Table 6.2.4-1, Sht. 2, Revision) .
(Sht. 6) Revision: Adds item 41a. This is a thennal relief valve as previously described.
(Sht.7) Revision: Adds item 52a. This is a thermal relief valve as previously described.
(Sht. 8) Revision: Adds items 60a and 61a. These are thermal relief valves as previously described.
(Sht. 9 and 9A) Revision: Adds new items 74a, 77a, 78a, 80a, 81a and 83a. These are thermal relief valves.
(Sht. 12) Revision: Adds items 114a, 120a and 121a. These are thermal relief valves as previously described.
Table 6.2.5-2 Correction: Provides the as-built hydrogen recombiner (Sht. 2) parameters.
Table 6.2.5-5 Correction: This change is to reflect current systems changes identified during the combustible gas control review. The remote thermal conductivity analyzers of the Containment Hydrogen Monitoring System were replaced by in-containment electrochemical sensors and microprocessor-based analyzers located in the control room.
Table 6.2.5A-2 Revision: Revises RCS total Hydrogen in 3rimary coolant (Sht. 1) 1191 SCF 1701 SCF this change is made to )e consistent with the Westinghouse Chemistry Criteria and Specification.
Attachment 6 to TXX-88040 January 15, 1988 Page 12 of 15 FSAR Page (as amended) Description Table 6.2.5A-3 Correction: Updates table to reflect additional aluminum electrical equipment in containment.
6.3 37 Clarification: The previous wordin Refueling Water Storage Tank (RWST)g is aligned implied that the to the suction of the S1 and RHR pumps at all times other than during refueling. This is not true for RHR cooling operations during Modes 4 and 5. Nor would it allow isolation and deactivation of the RWST suction to these pumps during Mode 5 operations (with the Reacto. Coolant System vented) which is desirable to prevent inadveitent overfilling of the RCS. This FSAR section has been revised to clarify the RWST alignment during specific plant operating modes.
6.4-1 Revision: This change revitas the allowable beta skin
.i for control room occupants during a LOCA, from 90 rem to 30 rem. Also, added statement that this allowable skin dose may be increased to 75 rem when special protective clothing and eye protection is used. This is a more conservative position than was previously stated and is consistent with NUREG-0800, Revision 2.
6.4-8 Correction: Deletes reference to the statement that smoke detection in the control room air intake causes the control room HVAC system to automatically shift to the isolation mode and to stop the operation of the control room emergency pressurization unit. Upon detection of I smoke the control room ventilation is manually shifted as
- stated in FSAR Section 9.4.1.3.
Revision: This change revises the allowable beta skin l dose from 90 rem to 75 rem (with special protective
- clothing and eye protection). (See Justification for page6.4-1).
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Attachment 6 to TXX-88040 .
January 15, 1988 l Page 13 of 15 i FSAR Page (as amended) Description 6.5-4 Revision: Clarifies the design of safety related ductwork by referencing ANSI N509-1980 as the ap3ropriate ;
standard for the specific allowable ductwork lea < age rates. The previous reference to "zero-leakage type" ;
ductwork was ambiguous and indetenninate. This revision j provides clear leakage criteria.
6.5-5 Clarification: Clarifies the instrument application of ESF filter units for recording and monitoring of flow ,
rates and pressure drops from the control room. '
6.5-11 Revision: This change revises the elevation of the lower ring nozzles from 1065 feet 11 inches to 1065 feet 10 l inches.
Correction: Changes the description of the nozzle !
orientation from "horizontally outward" to inclined ,
downward at angle of 45 degrees away from the containment !
center.
l 6.5-15 Revision: This chan I i
volumefrom2.985mi$erevisestheContainmentfree lion cubic feet to 3.031 million cubic feet, effective sprayed Containment volume from -
1.725 million cubic feet to 1.717 cubic feet, and the
,' fractional volume spray coverage from 57.8 percent to ;
56.7 percent. ;
6.5-16 Correction: This change corrects the minimum spray fall I height for Train A from 115 feet 9 inches to 117 feet 1 inch, and for Train B from 117 feet 1 inch to 115 feet 9
- inches.
1 6.5-17 Revision: Deletes the reference to "conservatively high estimate" for the containment free volume. The actual r free volume is revised from 2.985 million cubic feet to '
3.031 million cubic feet.
i 4 Revision: This change revises the total volume of Region A from 2.273 million cubic feet to 2.309 million cubic feet, the spray volume for Region A 1.669 million cubic j feet to 1.665 million cubic feet, and the Region A spray coverage from 73.4 percent 72.1 percent. .
6.5-18 Revision: This change revises the total volume of Region i 8 from 0.165 million cubic feet to 0.168 million cubic feet, and Region B spray coverage from 24.9 percent to :
24.4 percent.
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Attachment 6 to TXX-88040 I January 15, 1988 Page 14 of 15 i FSAR Page .
(as amended) Description ;
1 6.5-18 Revision: This change revises the total volume of Region ,
C from 0.072 million cubic feet to 0.073 million cubic
- feet.
Revision: This change revises the spray volume for Region D from 0.008 million cubic feet to 0.005 million cubic feet and the Region D spray coverage.from 6.4 percent to 4.3 percent.
Clarification: Provides an expanded description of_
containment "unsprayed volumes." l Revision: This change revises the total volume of Region ;
E from 0.350 million cubic feet to 0.356 million cubic '
feet.
6.5-20 Revision: Provides a description of the more realistic !
two region model used to describe the sprayed /unsprayed I 1 regions of containment. The overly conservative three i i region model used previously resulted in unnecessarily '
high control room doses. The two region model assumes ;
convective mixing between all sprayed and unsprayed '
volumes because of the numerous air flowpaths connecting these volumes. The specific assumption used, that mixing f occurs at the rate of two turnovers per hour, is consistent with the recommendations of NUREG-0800, Rev.
- 1.
2 6.5-26 Correction: Deletes the statement concerning horizontal !
! velocity component reducing drop exposure time, as this l
- statement is incorrect. e Table 6.5-1 Revision: This change revises the table to reflect and ,
i (Shts. 3 and 5) clarify the exception to NRC Regulatory Guide 1.52, for r l parts C.2.g and C.3.h (See Justification for page 1A(D)- !
l 21 and 1A(B)-22). !
i SER/SSER IMPACT: SER Sections 6.5.1.1, page 6-20, 4th paragraph; 6.5.1.2, page 6-21, first paragraph and l 6.5.1.3, page 6-21, and second paragraph indicates that, !
1 "the ESF exhaust filtration system is designed and meets .
l recommendations of NRC Regulatory Guide 1.52". By this !
FSAR-CR, SER needs to indicate the exception to Regulatory Guide 1.52, Revisions 1 and 2. j i
SSER No. 4, Section 9.4.4, page 9-2, first paragraph l indicates, "the safeguard ventilation system meets the ,
requirements of part C.2 of NRC Regulatory Guide 1.52". [
j By this FSAR-CR SER needs to be revised to indicate the !
, exception to NRC Regulatory Guide position C.2 9 '
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Attachment 6 to TXX-86040 January 15, 1988 ,
Page 15 of 15 i
FSAR Page Lasamended) Description ,
Table 6.5-5 Revision: This change revises the Table to reflect >
4 volume changes provided previously in the text revisions (Section 6.5).
Revision: This change revises the Table to be consistent with the two region containment spray model (See Justification for page 6.5-20),
i Corr 3ction: Revises the spray drops fall height to be L consistent with the height provided in the text.
Correction: Revises the number of nozzles per train to be consistent with the numbers provided in the text. :
Clarification: Provides clarifying footnotes.
Section 6.6 Editorial: Section 6.6 is being reissued with new format for change bars and sheets renumbered with typographical 4
errors corrected. l 1 ;
6.6-1 thru See Justification for page 3.98-44.
6.6-3
- 6.6-3 Addition
- Adds new Section 6.6.8 describing augmented I inservice inspection requirement.
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Attachment 7 to TXX-88040 1 January.15, 1988 {
, Page 1 of 7 r
DETAILED DESCRIP110N t
FSAR Page i i (as amended) Description l
Section 7.1 Editorial: This section is being reissued in the !
computerized format, j 7.1-10 Correction: Adds the UPS ventilation system to the ESF 4
support systems to be consistent with other such listings i in Chapter 7.0 of the FSAR. !
7.1-10 and Correction: Clarifies the distinction between NSSS and 7.1-15 B0P Class 1E Uninterruptible Power Supplies (UPS). To be consistent with Section 8.3 of the FSAR, the UPS for the ,
i NSSS Reactor Protection System will be titled "Class 1E 118VAC UPS" and the UPS for 80P systems will be titled ,
"Class 1E Static UPS" to avoid confusion when referencing i these systems. :
7.1-12 Editorial / Correction: Revises text to be consistent with revisions made to Section 7.5. t 7.1-25 thru Addition: Adds reference to WCAP-8892-A, "Westinghouse !
- 7.1-27 7300 Series Process Control System Noise Tests," June ;
i 1977, for the BOP Analog Instrumentation System, which .
was previously omitted. The report demonstrated that the f train orientation and wiring techniques used in the 7300 !
process control system meet the requirements of v
, Regulatory Guide 1.75 and have been accepted by the NRC. t I
7.1-41 Revision: Clarification to reflect that the Safety System inoperable Indication audible alarm is sounded !
1 only during bypass activities which are automatically j indicated. An alarm is not included for bypass i
] activities for which the indication is activated by the t
- operator. !
3 9 l 7.1-43 Correction: Adds the UPS ventilation system to the ESF support systems to be consistent with other such listings f j in Chapter 7.0 of the FSAR. t 1
Table 7.1-2 Correction: Deletes applicability of Regulatory Guide l t
(Sht. 2) 1.105 for containment isolation. The actuating signals t for the containment isolation functions are inherent to the ESF actuating system (i.e. safety injection, f containment spray, etc.), and therefore any applicability :-
of these setpoints per the Regulatory Guide are noted j under the individual function, j
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Attachment 7 to TXX-88040 l January. 15, 1988 ;
Page 2 of 7 :
FSAR Page !
, (as amended) Description i
Section 7.2 Editorial: This section is being reissued in the '
computerized format.
7.2-19 Revision: Describes the functional removal and capping :
i of the RTD bypass manifold connections (See Justification '
for Table 5.2-2, Sht. 3).
i Section 7.3 Editorial: This section is being reissued in the !
computerized fonnat. ,
7.3-8 and Clarification: Clarifies difference between Containment 7.3-10 Spray System and pump actuation. A P-signal or manual start will start the pumps and initiate spray inside -
containment. However, an S-signal only starts the pumps !
in recirculation mode. >
7.3-11, 7.3-12 Editorial / Correction: Revises text to be consistent with i 7.3-18 and revisions made to section 7.5. "
7.3-22 r
7.3-?8 Correction: Deletes the Auxiliary Feedwater Pumps low !
pump suction pressure as an interlock to match the as built plant design. These pressure switches as installed
- i were disabled due to their potential to cause spurious -
3 trips and disable the Auxiliary Feedwater System. :
)
7.3-29, 7.3-31 Editorial / Correction: Revises text to be consistent with J
7.3-33, 7.3-36, revisions made to section 7.5.
7.3-39 thru 7.3-41, 7.3-44, and 7.3-45 t
7.3-63 Correction: Previously, it was implied that the UPS i Ventilation System provides input to the plant computer, i which it does not. Therefore, the reference to the plant
} computer points were deleted, i 1
7.4-19 and Addition: Adds Control Room HVAC Mechanical Equipment I j 7.4-21 Room to the description of Alternate Shutdown Areas to !
l accurately reflect design. l Clarification: Inclnded in the description of shutdown !
I locations, the Local Controls to clarify locations of >
! required actions. !
7.4-22 Correction: Adds "Train B" transfer switches into the [
j discussion of electrical isolation of components between l 1 Hot Shutdown Panel (HSP) and Control Room circuits. This i
reflects "as-built" conditions and the use of Train A equipment required for operability as well as those i required Train A and Train B switches for equipment which ;
l are credited to mitigate and/or prevent potential {
! spurious operations, l l l l
Attachment 7 to TXX-88040 January 15, 1988 Page 3 of 7 ,
FSAR Page (asamended] Description 7.4-22 Clarification: Clarifies control circuits as isolated from Control Room by use of transfer switches positioned in the as-marked "HSP" position.
Clarification: Deletes statement concerning cable runs external to the HSP because it adds nothing to the protection schemes presently employed.
Clarification: The HSP and Alternate Shutdown operability is only required in specific areas of the plant. This completes the statement for those areas requiring the HSP by describing that the loss of control circuit occurs in the Control Room / Cable Spreading areas.
Clarification: Clarifies that the single event is a fire ,
and that this design requirement does not apply to all redundant systems, but only to those systems required for alternate shutdown capability.
7.4-26 Addition: Adds Control Room HVAC Mechanical Equipment Room to the description of Alternate Shutdown Areas to reflect "as-built" design.
Clarification: Clarifies that this provision is applicable to only required Train A circuit controls being transferred.
Clarification: Clarifies that the "required" Train A and/or required Train B "fire safe" shutdown control circuits and "process" monitoring circuits are independent of all the "Alternate Shutdown Areas".
Tables 7.4-1 thru Clarification: Clarified the description of switches to 7.4-3 reflect current design.
Section 7.5 Editorial: Section 7.5 is being reissued with new format for change bars, sheets renumbered, and typographical errors corrected.
7.5-1 Clarification: Accident monitors are based on emergency response procedures.
- 7.5-3 Clarification: Changes the Category I display description from "immediately accessible" to "continuous" to be more precise.
7.5-4 Update: Revises list of critical safety functions to match the emergency response procedures. No change in content.
-Attachment 7 to TXX-88040 i January 15, 1988
- L Page 4-of 7 FSAR Page $
(as amended) Description
7.5 Update
Adds a definition for preferred backup variables. >
Update: Adds a definition for diverse variable as used ,
j in this section. !
7.5-7 See Justification for page 7.5-4. f 7.5-8 Clarification: Revised the description for the Type E variables to be more concise. ,
7.5-9 Clarification: Changes the description of operator action from N ecessary" to "preplanned" to be more i
- j. precise.
- i i i 7.5-10 Clarification: Changes to denote that at least one Category 1 channel uses a direct-indicating display. ,
Revision: Oclete discussion on redundant sensor checking by ERF Computer since the actual potential for using this :
method is small. i 1
Clarification: Deletes discussion of containment !
isolation valves for they are not Category 1.
7.5-12 Clarification: Provides a mare specific commitment with respect to Category 1 equipment testing as previously
)
t
.l submitted in response to question 0032.110. ;
7.5-13 Clarification: Describes, more specifically, the
- portions of Category 2 channels which are seismically l qualified. ,
j 7.5-14 Clarification: Revised discussion on testing to match ;
4 position previously submitted in response to question ;
QO32.110. ;
7.5-17 Revision: Deletes "Wide Range Steam Generator Level" i t
adds RCS Subcooling (Saturation Margin) as a Ty]e A :
Category 1 variables since it is relied up in t1e revised '
f Emergency Response Procedures for preplanned operator ;
j actions. y 1 i Clarification: Revise parameter titles to more clearly ;
, describe the parameters. .
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7.5-18 Clarification: Revises parameter titles to more clearly l describe the parameters. '
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Attachment-7 to TXX-88040 ,
January 15, 1988 -
Page'5 of 7
?
FSAR Page (asamended) Description. l l
7.5-18 Revision: Deletes the parameter Containment Radiation [
Level from the list of Type A parameters for no ;
preplanned operator actions will be based on this-
- parameter in the Emergency Response Procedures. l Clarification: Revises discussion on the category of Type A variables to use a positive statement.
See Justification for page 7.5-4.
7.5-19 7.5-20 Clarification: Changes "information" to "variables" I
- which is a more precise term.
7.5-21 Clarification: Changes "information" to "variables" which is a more precise term.
Clarification: Revises titles of some of the systems I covered by Type D variables to better describe the systems. '
l 7.5-22 Revision: Designates Containment Radiation Level as
- Category 1 to be consistent with Regulatory Guide 1.97. .
! Table 7.5-1 Clarification: Deletes "Testability" and "Channel out of Service" items because their meanings are ambiguous in the table. Testing and channel out-of-service provisions are adequately discussed in the text.
l Clarification: Revised title to note that the table is a i
- list of minimum requirements. Other table entries are
- revised to be consistent with text. !
l Table 7.5-2 See Justification for Page 7.5-17.
] Table 7.5-3 See Justification for Page 7.5-4. !
! Revision: Deletes "Secondary System Radiation *" with its l associated footnote, and listed the individual parameters
-Condenser Off - Gas Radiation and S/G Blowdown Radiation l Level. Main Steamline Radiation was deleted because it j is not a timely monitor for the required functions. ;
4 5
Revision: Revised the list of parameters to reflect the !
"status trees" used in conjunction with the Emergency l l Response Procedures as noted. !
1 Table 7.5-4 Clarification: Revised the title of the first function I
- to fuel Cladding to better describe the function being [
j monitored. [
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Attachment 7 to TXX-88040 January 15, 1988 Page 6 of 7 FSAR Page lasamended) Description Table 7.5-4 Revision: Revised Adjacent Building Radiation parameter from a primary backup to a backup variable for the Containment Boundary function. This revision changes the type / category for this parameter from C2 to C3. This change is consistent with US NRC Regulatory Guide 1.97, Revision 3, which does not list this parameter as a Type C variable.
Revision: Concerning Secondar Justification for Table 7.5-3)y Systems Radiation (See Clarification: Revises variable name to "Accident Sampling" to better describe the variable.
Revision: Deletes "Radiation level in Circulating Primary Coolant." CPSES does not use this parameter for accident monitoring. This deviation from Regulatory Guide 1.97, Rev. 2 is discussed in the revised Table 032.110-4.
Revision: Deletes pressure relief tank variables as they should not be Type C variables.
Revision: Clarifies which Containment isolation Valves are monitored.
Table 7.5-5 Revision: The entire table has undergone many changes as a result of a CPSES initiated study of the proper Type 0 variables. Several variables have been added.
Pressurizer heater breaker position has been replaced with "Heater Current" as a 02 variable. RCS Pump Motor Current changes from D2 to 03 which is consistent with Regulatory Guide 1.97, Rev. 2.
Revision: Changed "Control Room Ventilation" to "ESF Ventilation" and listed the individual parameters that are monitored to be more precise.
Addition: Added Safety injection, RHR, Centrifugal Charging, Auxiliary feedwater, Containment Spray, CCW and SSW pump statuses as Type 02 key variables.
Table 7.5-6 Revision: Changes "Containment Radiation Level" to Category 1 to be consistent with Regulatory Guide 1.97, Rev. 2.
l Revision: Changes the category for meteorological parameters from Category 2 to Category 3. These l parameters have been designated as backup variables, in l
a similar manor, Environs Radiation has also been changed to Category 3, backup. These variables backup the radiological release parameters. This change is consistent with Regulatory Guide 1.97, Rev. 2.
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A',tachment 7 te TXX-88040 January 15, 1988 Page 7 of 7 FSAR Page (as amended) Description Table 7.5-7 Revision: Updates this table to reflect the changes made in Tables 7.5-2 thru 7.5-6 and as-built technical changes.
Revision: Reflects EQ requirements for Hain Steam Line Radiation, Steam Generator Blowdown and Cnndenser Of f-Gas Radiation.
Section 7.6 Editorial: This section is being reissued in the computerized format.
7.6-1 Correction: Clarifies the distinction between NSSS and 80P Class IE Uninterruptible Power Supplies (UPS). To be consistent with section 8.3 of the FSAR, the UPS for the NSSS Reactor Protection System will be titled "Class IE ll8VAC UPS" and the UPS for the B0P systems will be titled "Class IE Static UPS" to avoid confusion when referencing these systems.
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= Attachment 3 to TXX-88040 l January 15, 1988
'Page 1 of 9 CPSES FSAR AMENDMENT 66 DETAILED DESCRIPTION FSAR Page (as amended) Description Sections 8.1, 8.2 These sections have been revised to reflect the and 8.3 addition of two startup transformers (IST & 2ST) to feed the non-safety related 6900-V buses. The two new startup transformers are powered from the 345 kV Switchyard. The existing startup transformers (XST1 & XST2) are now dedicated sources of preferred and alternate power directly feeding the safety related 6900-V buses. All four transformers have similar electrical ratings except that IST and 2ST will have an impedance of approximately 5's instead of approximately 8.5's. The spare transfonner can be used to replace any of the four startup transformers.
XST1 and XST2 no longer serve as the startup power supply for the non-safety related 0900-V buses. IST and 2ST now serve as the startup power supplies for the non-safety related 6900-V buses for Unit I and Unit 2, respectively. The safety relatea 6900-V buses can no longer be connected to an cffsite power source by backfeeding them through the main step-up transformer and unit auxiliary transformer; however, the non-safet; related 6900-V buses retain this feature.
2ST will he installed prior to startup of Unit 2.
This design modification improves the offsite power system reliability by 1) sepcrating the non-safety related 6900-V buses from the safety related 6900-V buses, 2) reducing the load requirements on the startup transformers and thereby increasing the available voltage under design accident loading conditions, and 3) reducing the influence of grid related voltage fluctuations (i.e.,
the grid will have to reach a lower voltage level to reach the same minimum allowable voltage on the safety related buses). The design modification also resolves potential deficiencies identified during the recent design review process concerning transformer overloading and equipment voltage levels under worst case design accident load scenarios.
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Attachment 8 to TXX-88040 January 15, 1988
.Page 2 of 9 FSAR.Page (asamended] Description Sections 8.1,.8.2 These sections are being reissued due to the text shifts and 8.3 involved with the number of changes. Minor editorial corrections have been included in the reissue.
8.1-2 Revision: Revised to reflect the addition of two startup transformers (IST & 2ST) to feed the non-safety related 6900-V buses. The twc new startup transformers are powered from the 345 kV Switchyard. The existing startup transformers (XST1 & XST2) are now dedicated sources of preferred and alternate power directly feeding the safety related 6900-V buses. The safety related 6900-V buses can no longer be connected to an offsite power source by backfeeding them through the main step-up transformer and unit auxiliary transformer; however, the non-safety related 6900-V buses retain this feature. (See general discussion above).
8.1-4 thru Correction: Corrects followin 8.1-6 consistent with Appendix 1A(B)g of FSAR: discrepancies (1.) Reg.to be Guide 1.2o should be Revision 2, February 1976, (2) Reg. Guide 1.40 is not applicable to CPSES and is deleted, and (3)
Reg. Guide 1.81 should be Revision 1, January 1975. The remaining items in this list have been appropriately renumbered to reflect the deletion.
8.1-7 Revision: CPSES will use IEEE Std. 450-1980 rather than the 1975 version for compliance with Reg. Guide 1.129.
(See Justification for page 1A(B)-71).
Table 8.1-1 Editorial: Table reissued with text shifted.
Table 8.1-1 Revision: Deletes emergency lighting since the AC (Sheet 3) Essential Lighting System and DC Emergency Lighting System are reclassified as non-Class lE (See Justification for page IA(B)-45).
8.2-1 Revision: The safety related 6900-V buses can no longer be connected to an offsite power source by backfeeding them through the main step-up transfonner and unit auxiliary transformer; however, the non-safety related 6900-V buses retain this feature. (See general l discussion above for Sectiens 8.1, 8.2 and 8.3).
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Attachment 8 to TXX-88060 January 15, 1988 Page 3 of 9-FSAR Page (as amended) Description 8.2 6 Revision: Revised to reflect the addition of two startup transformers (IST & 2ST) to feed the non-safety related 6900-V buses. The two new startup transformers are powered from the 345 kV Switchyard. The existing startup transformers (XST1 & XST2) are now dedicated sources of preferred and alternate power directly feeding the safety related 6900-V buses. The safety related 6900-V buses can no longer be connected to an offsite power source by backfeeding them through the main step-up transformer and unit auxiliary transformer; however, the non-safety related 6900-V buses retain this feature. (See general discussion for Sections 8.1, 8.2 and 8.3).
The spare startup transformer now has an air switch on the "high" side and the transformcr can replace any of the four startup transformers.
8.2-7 Revision: Revised to reflect the addition of two startup transformers (IST & 2ST) to feed the non-safety related 6900-V buses. The two new startup transformers are powered from the 345 kV Switchyard. The existing startup transformers (XST1 and XST2) are now dedicated sources of-preferred and alternate power directly feeding the safety related 6900-V buses. The safety related 6900-V buses can no longer be connected to an ofisite power source by backfeeding them through the main step-up trar.sformer and unit auxiliary transformer; however, the non-safety related 6900-V buses retain this feature. (Seegeneral discussion for Sections 8.2, 8.2 and 8.3).
Adds description of control for motor-operated air switch used for the spare transformer. Control of this air switch from the control room is not required since the transformer cannot be put into service strictly from the control room.
Short sectior:s of ventilated solid top cover, cable tray are used in the modification as well as the previously existing metal-enclosed, ventilated, solid top cover, cable bus ducts.
8.2-8 Revision: Revises discussion on fire for bus ducts / cable trays. Certain sections pass through electrical equipment rooms which are not "inaccessible." The CPSES Fire Protection Program has provided adequate protection to ensure safe shutdown can be achieved for any firss that effect both preferred and alternate power source bus ducts / cable trays.
Attachment 8 to TXX-88040 January 15, 1988 Page 4 of 9 FSAR Page (as amended) Description 8.2-8 Revision: Revised to reflect the addition of two startup transformers (IST & 2ST) to feed the non-safety relaterl 6900-V buses. The two new startup transformers are powered from the 345 kV Switchyard. The existing startup transformers (XST1 & XST2) are now dedicated sources of preferred and alternate power directly feeding the safety related 6900-V buses. (See general discussion above for Sections 8.1, 8.2 and 8.3).
8.2-10 Revision: The safety related 6900-V buses can no longer be connected to an offsite power source by backfeeding them through the main step-up transformer and unit auxiliary transformer; however, the non-safety related 6900-V buses retain this feature. (See general discussic,n above for Sections 8.1, 8.2 and 8.3) .
8.2-14 Revision: Revised to reflect the voltages calculated for and 8.2-15 the new system arrangement and to place the listed voltages in a logical order.
8.3-1 thru 8.3-7, See Justification for page 8.1-2.
8.3-10, 8.3-11 and a.3-13 8.3-1 Revision: The AC Essential Lighting System is reclassified as non-Class 1E. Lighting is not a safety related function.
The AC Essential Lighting System is fed from safety related buses. It is isolated from the Class 1E power ;
sources with two se3arate Class 1E breakers connected in series. These brea<ers are coordinated with their supply breaker and will be tested periodically. The circuits are routed in conduit to provide physical and electrical independence beyond the isolation breaker. The conduit meets the separation criteria given in Section 8.3.1.4.
8.3-2 Correction: Item 4 on page 8.3-6 was not previously
- identified.
8.3-3 Correction: There are f've transmission lines feeding the 345 kV Switchyard.
8.3-4 and Revision: Deletes discussion on overloading startup 8.3-5 transformer since this no longer occurs with the startup transformer modificaton. Each startup transformer has the capacity to carry the required Class 1E loads of both Units during all modes of plant operation, which includes DBA's. The transfer of loads will always be sequenced and will not occur as a step function.
Attachment 8 to 1XX-88040 January-15, 1988 Page 5 of 9 FSAR Page
-(as amended) Description 8.3-6 and Revision: .This change revises the description of the 8.3-7 power sources for common bus XA1 due to the new startup transformer modification.
There is no interconnection now between safety related and non-safety related 6900-V buses.
8.3-9 Clarification: Clarifies actual panel voltages associated with the 120-VAC distribution panels' specification.
Correction: This change corrects the Class and Interrupting Current listed for 120-VAC panels to reflect the specification.
8.3-13 Revision: The plant Technical Specifications describe the Limiting Conditions for Operation and time constraints for the offsite power supply. Reg. Guide 1.93 is not intended to be site specific or to take the place of the Technical Specifications.
8.3-14 Clarification: The sequencer sequentially loads the safeguard buses onto the diesel generator. The current NRC terminology for the CPSES term "blackout" is "Loss of Offsite Power."
Revision: The AC Essential Lighting System is reclassified as non-Class 1E. The AC Essential Lighting System is fed from safety related buses. It is isolated from Class 1E power sources with two separate Class 1E breakers connected in series. These breakers are coordinated with their supply oreaker and will be tested periodically. The circuits are routed in conduit to provide physical and electrical independence beyond the isolation breaker. The conduit meets the separation criteria given in Section 8.3.1.4.
8.3-15 Clarification: Adds "Loss of Offsite Power" in reference to "blackout" to reflect the current NRC terminology.
Revision: Deletes discussion on 7000 kW electric boiler since the startup transformers are no longer overloaded.
8.3-17 Correction: Corrects the description for ammeters used in the Control Room and on the hot shutdown panel. The Control Room ammeters are not transducer-driven. The hot shutdown panel has one ammeter for each Standby Power Source.
Attachment 8 to TXX-88040 January 15, 1988 Page 6 of 9 FSAR Page (as amended) Description 8.3-17 Clarification: This change clarifies the locations-of selector switches and diesel generator breaker control switches.
Clarification: Clarifies the locations of control switches for 6900V and 480V switchgear circuit breakers.
These described locations are consistant with the plant one-line diagrams.
8.3-39 Addition: Adds design reference for mechanical portion of electrical penetrations.
8.3-43 See Justification for page 8.2-10.
8.3-44 thru Editorial: Deletes references to Figures 8.3-18 8.3-48 through 8.3-45 which are being deleted.
8.3-50 Revision: Revises tLe discussion on time current curves and deletes reference to Figure 8.3-45. Figures 8.3-18 through 8.3-45 are being deleted. The adequacy of penetration protectiN devices to protect the penetrations is established by detailed calculations.
These calculations compare the time current characteristics of protected devices against penetration capability curves. These calculations are available at the site. The time current characteristics curves represent highly detailed design information which is not required to be included in the FSAR.
8.3-54 and Revision- The AC Essential Lighting System and DC 8.3-55 Emergency Lighting System are reclassified as non-Class 1E. Lighting is not a safety related function.
The AC Essential Lighting System is fed from safety related buses. It is isolated from the Class 1E power sources with two se)arate Class 1E breakers connected in series. These brea<ers are coordinated with their supply breaker and will be tested periodically. The circuits are routed in conduit to provide physical and electrical independence beyond the isolation breaker. The conduit meets the separtion criteria given in Section 8.3.1.4.
The DC Emergency Lighting, which was previously fed from Llass 1E station batteries, will be fed from dedicated non-Class 1E batteries. These circuits are also routed in conduit to provide physical and electrical independence from Class 1E circuits. The conduit meets the separation criteria given in Section 8.3.1.4.
e to TXX-88040 January 15, 1988 i Page 7 of 9 FSAR Page lasamended) Description 8.3-55 Revision: Adds exception to Reg. Guide 1.75 Regulatory Position C.1 for the non-Class 1E diesel generator neutral grounding transformer. This transformer is connected to the neutral of the Class 1E diesel generator. An analysis has been performed which demonstrates that a fault on the non-Class 1E portion of-the circuit will not cause an unacceptable influence on-the Class 1E system.
8.3-59 Correction: Deletes statement concerning environmental effects. The environmental parameters for Class 1E equipment are Jefined in FSAR Section 3.11.
8.3-62 Addition: Adds design reference for mechanical portion of electrical penetrations.
8.3-t5 Revision: Revised to reflect the method of compliance with 1EEE Std. 494-1974. The phrase "Class 1" is used, in lieu of and as equivalent to the phrase "Nuclear Safety Related" to identify safety related drawings and documents.
8.3-66 Revision: Deletes the minimum separation requirements listed between distribution panels of redundant trains and channels locatad in the cable spreading room. There was no regulatory basis for this requirement and the separation requirements for redundant raceway will e,1sure the adequacy of panel scparation.
8.3-66 and Revision: Adds an exception to Reg. Guide 1.75 8.3-67 Regulatory Position C.12 for listed components which are not high energy equipmrnt but are loctted inside the Cable Spreading Room / Control Room complex and have power circuits outed in exclusive conduits within the Cable Spreading Room / Control Room compicx, 8.3-71 Addition: Clarifies the separatim requirement for fiber optic cables, as fiber optic celes carry no electrical energy by themselves, they are not required to maintain physical separation between non-Class 1E and Class 1E circuits.
8.3-73 Addition: Adds Glastic bc ids to description of internal materials. Glastic boards are ut.ed as barriers inside control panels. Those used are grades UTS or UTR. Flame resistance properties of these grades meet UL94-VO which meets the requirements for self-extinguishing materials classified by ASTM Std 0635-1972, nhich is the requirement of IEEE Std 420-1982 for flame retardant materials used in control panels, and which is referred to by lEFE Std 420-1973 which applies to CF3ES.
Attachment 8-to TXX-88040 January 15, 1988 Page 8 of 9 FSAR Page (as amended) Description 8.3-73 Revision: Specifically identifies the NSSS inverters which have integrally associated cables. Adds to the description specifically identified "balance of plant" inverters which do not require separation since the associated circuits involved are isolated by a Class IE breaker tripped by an "S" signal (i.e., the associated circuit meets the separation requirements of Reg. Guide 1.75 for non-Class IE circuits). Details are provided in Table 8.3-10.
8.3-76 Clarification: Clarifies that normal cable tray construction gaps do not violate separation cirteria.
8.3-79 See Justification for page 8.3-71.
8.3-80 Revision: The DC Emergency Lighting System is ,
reclassified as non-Class 1E. Lighting is not a safety related function.
The DC Emergency Lighting, which was previously fed from Class IE station batteries, will be fed from dedicated non-Class IE batteries. These circuits are also routed in conduit to provide physical and electrical independence from Class IE circuits. The conduit meets the separation criteria given in Section 8.3.1.4 8.3-85 Correction: Adds reference to new Tables 8.3-48 and 8.3-4C. See Justification for Tables 8.3-4 through 8.3-4C.
8.3-88 Revision: Revised to reflect the method of compliarce with IEEE Std. 494-1974 which is discussed in Section 8.3.1.4. The phrase "Class 1" is used in lieu of and as ec uivalent to the phrase "Nucle'.r Safety Related", to icentify safety-related drawings and documents.
8.3-89 thru Revision: Clarifies raceway fill criteria used for 8.3-91 CPSES. Revises title from cable "tray" to "raceway" to include conduit. Adds instrumentation cables to discussion. Revises cable tray fill criteria discussion, references IPCEA P-46-426 for criteria, and deletes reference to the NEC. Adds information on requirements for rible fill for conduit. The new conduit fill requirements are a simplification of those contained in the NEC.
( 8.3-98 Addition: Adds design reference for mechanical portion i cf electrical penetraticns.
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Attachment-8 to TXX-88040 January 15, 1988 Page 9 of 9 FSAR Page (as amended) Description Table 8.3-1A Update: Updates table to reflect the current design
-loads. Editorial corrections made for clarity.
Table 8.3-18 Update: Updates table to reflect the current design loads. Editorial corrections made for clarity.
Table 8.3-2 Update: Updates table to reflect the current design ,
loads. Editorial corrections made for clarity.
Revision: Revises table to reflect installation of three new instrument air units (one of these units is fed from a non-safety-related bus). Adds two new notes clarifying information related to the instrument air system.
Clarification: Adds "Loss of Offsite Power" in all references to "blackout" to reflect the current NRC terminology.
Table 8.3-3 Revision: Revises the table to reflect the installation of new startup transformers for the non-Class 1E loads (offsite power supply design modification). Adds equipment designators for clarity.
Editorial corrections made to correct typographical errors and improve clarity.
Tables 8.3-4 thru Revision: Tables 8.3-4 and -4A are being revised and 8.3-4C Tables 8.3-48 and -4C are being added to: (1) reflect the latest load data for the current CPSES design and (2) reflect the differences in loading between Trains A and B.
Table 8.3-7 Correction: This change corrects the FEMA table for (Shts. 1 and 2) proper effects on system given single failure analysis for failure of a battery charger, 600-V cable from battery charger to switchboard or feeder breaker connecting battery charger to switchboard.
Tables 8.3-8 and Updates: Updates the 6900-V and 480-V load tables 8.3-9 to reflect the current design.
Table 8.3-10 Revision: Adds "balance of plant" inverters not requiring separation since their associated circuits are isolated by a Class 1E breaker tripped by an "S" signal (See Justification for page 8.3-73) .
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Attachment 9 to TXX-88040 January 15, 1988 Page 1 of 20 CPSES FSAR AMENDMENT 66 DETAILED DESCRIPTION FSAR Page (as amended) Description Section 9.1 Editorial: lhis section is being reissued in the computerized format.
9.1-13 Revision: CPSES has six Single Failure Proof (SFP) seismic Category I cranes and hoists. Four of these SFP cranes are the two containment polar cranes and the two fuel building overhead cranes. The phrase "Single Failure Proof" indicates that a hoisting system is designed to safely retain a specified lifted load with a single failure in the system.
The fuel building overhead crane discussion has been updated to reflect a seismic Category I classification instead of seismic Category II. A seismic Category I classification for SFP cranes and hoists at CPSES indicates the functional requirement that the lifting device be able to raaintain structural integrity and safely retain the lifted load during and after specified seismic events. This seismic classification provides additional assurance of the capability to retain lifted loads beyond the SFP design feature.
9.1-33 Revision: Revision reflects the requirements for determining boron concentration of the Reactor Coolant System and the refueling canal from daily to every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> as per NUREG-0452, the Westinghouse Standard Technical Specifications, and the CPSES proposed Technical Specifications submitted October 30, 1987.
9.1-46 Revision: The polar crane and fuel building overhead crane discussion has been updated to reflect a seismic
' Category I classification instead of seismic Category II.
(See the discussion for page 9.1-13.) An update is also provided to reflect the correct FSAR cross-references.
9.1-57 Clarification: An editorial correction is provided to reflect that the polar crane has a maximum "critical" load of 175 tons (instead of "noncritical"). Also, the discussion of WCAP 9198 (Reference [16]) is deleted because this report is not applicable to CPSES.
! 9.1-58 Correction: The discussion of WCAP 9198 (Reference [16])
is deleted because this report is not applicable to CPSES.
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,_ to TXX-88040 January 15, 1988 Page 2 of 20 FSAR Page (as amended) Description 9.1-60 Revision: An u)date is provided for the containment polar and fuel ]uilding overhead cranes, which represents
.these cranes as seismic Category 1. (See the discussion for page 9.1-13.) The update also. reflects that the loading combinations for the fuel building overhead crane includes OBE and SSE with lifted load. The loading combinations for the polar crane includes OBE with lif ted load and SSE without lifted load.
Correction: This change corrects the text to read as, "2.5 mrem /hr or less", as per Westinghouse radiation analysis design manual SPM 412, Revision 3, page 5-58.
9.1-67 Correction: Reference to WCAP 9198 is deleted because this report is not applicable to CPSES.
Table 9.1-3 Revision: Revises the maximum flow of s)ent fuel (Sht. 2) pool demineralizer and filter based on t ie revised calculation.
Correction: Revises perforation size of spent fuel pool suction screen from 0.1 in. to 0.08 in. to match as-built conditions.
(Sht.3) Correction: Changes the purification loop resin trays perforation size from 0.5 mm to the actual size of 0.14 mm.
Section 9.2 Editorial: This section is being reissued in the computerized format.
9.2-1 Revision: Deletes the SSW supply to the Fire Protection Booster Pumps, as CPSES design no longer includes Fire Protection Booster Pumps.
SER Section 9.2.1, on page 9-8, 1st paragraph indicates, the "SSW can be used as a back-up Water Supply for the Fire Protection Booster Pumps" by this FSAR-CR, SER needs to be revised to delete the SSW back-up source to Fire Protection booster pumps.
9.2-3 Revision: This change revises the system operating description to reflect the operation of both SSW pumps to minimize the corrosion due to stagnant flow.
9.2-4 Revision: Describes the addition of the use of a toxic non-oxidizing blocide for the control of Asiatic clams and corrosion inhibitor in the Station Service Water System.
Revision: Revised to reflect the deletion of SSI water, "and to be noncorrosive" as the meaning of this phase was unclear.
Attachment 9 to TXX-88040 January 15, 1988 Page 3 of 20 FSAR Page (as amended) Description 9.2-5 Revision: Revises to reflect both pumps of Train "A" and Train "B" operation (See Justification for page 9.2-3).
9.2-9 Revision: Revises to delete the epoxy based lining in order to prevent sheet mode failure, which can plug safety related heat exchangers served by SSW System.
SER Section 9.2.1, Page 9-8, 5th para, indicates, "The SSW one train operates at all times in normal operation.
In the event of failure of any component in one train, another redundant train automatically starts in 60 seconds." By the FSAR-CR, SER needs to be revised to reflect that both trains of SSW operate at all times to minimize corrosion.
9.2-16 Revision: Adds 'q', reactor coolant post-accident sampling system sample cooler to the list of the components cooled by non-safety loop of Component Cooling Water System. This change is already processed earlier by Amendment 36 (TMI Il-B-3) and Amendment 54 (Figure II.B.3-1). Change 'p' to 'q' by addition of 'q' (see above).
9.2-19 Clarification: Clarifies the operation of surge tank when it overflows due to extreme surges, and routes the excess flow to the floor drains.
9.2-22 Correction: This change reflects that tubes are "rolled into" in lieu of "welded to" the tube sheet.
Clarification: Adds a summary description of the CCWS Surge Tank control functions and operator action in the event of excessive surges in the CCWS.
9.2-23 Revision: Revision reflects the addition of stainless steel material for relief valves, as certain heat exchangers served by CCW's are protected by stainless j steel relief valves.
9.2-29 Revision: Deleted the low flow alarms for the control room air-condition condensers, as the cooling water flow I
is regulated by refrigerant pressure.
9.2-31 Revision: This revision reflects the addition of handwheels to the level control valves to the CCW surge l tank, which provides the capability of providing the I make-up water in the event of loss of instrument air to the control valves.
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. _ _ to TXX-88040 January 15, 1988 Page 4 of 20 FSAR Page (as amended) Description 9.2-31 Revision: Revised the Chilled Water System condenser control to automatic control, actuated by refrigerant pressure. In the event of loss of air, Accumulator Backup Tank is added, and the valves are provided with handwheel for operator action.
9.2-32 Revision: Adds CCW regulating valves which control CCW flow to/around the Ventilation condensers based on a pressure indicating controller on the refrigerant side of the condenser. This change allows the operation of ventilation chillers to cool plant equipment during the winter month.
9.2-33 Revision: Upgrades the CCS flow instrumentation to class 1E to provi d isolation CCW to RCP thermal barrier following thermal barrier tube rupture.
9.2-35 Revision: Deletes the operator action to close the vent valves at CCWS Surge Tanks, because CCW surge tank relief capacity is provided.
SER Section 9.2-2, page 9-10, 4th paragraph indicates, "Radiation monitors are designed to actuate alarm in the control room on high activity level and close the Surge tank and drain tank atmospheric vent valves". Due to this FSAR-CR, SER needs to revise the deletion of closing the vent valves at CCWS surge tanks.
9.2-36 Revision: This change reflects the addition of the demineralized water source to perform turbine generator primary flow rate testing during refueling outages.
9.2-53 Revision: Describes the modification of CSf high level Control, which prevents CST overpressurization in the event of condenser surge by isolating the makeup and reject line on CST Hi-Hi level. The condenser hot well is designed to the postulated taken surges in the event of CST high level.
SER Section 9.2-6, page 9-14, 1st paragraph indicates "CST provides surge capacity for secondary system inventory changes caused by different operational conditions..." By this FSAR-CR, SER needs to be revised to delete the Surge capacity of CST.
Table 9.2-3 Revision: Adds additional corrosion inhibitors, to the list of inhibitors to be qualified for use in the CCW system to provide a more effective corrosion protection program for CCW system.
Attachment 9 to TXX-88040
. January 15, 1988 Page 5 of 20 FSAR Page (as amended) Description Table 9.2-10 Revision: Revision reflects the change in total Suspended Solids to a more conservative value of 'less than 0.05 PPM' for RMUW system as per Westinghouse system design-criteria Specification (PIP. Vol 5-1).
Clarification: Clarifies the foot note as it applies to RCS and not steam supply s,* em and also the oxygen concentration limit of 0.1 PPM applies when the RCS temperature is greater than 1800F (not the makeup water temperature).
Correction: Deletes "and the steam space" since the oxygen content refers only to the RCS, Correction: Replaces "makeup" with "reactor" since it is the RCS coolant ter;;perature which determines when makeup water can be above 0.1 ppm oxygen. The above changes are consistent with the Westinghouse Project Information Package "Chemistry Criteria and Specifications".
Section 9.3 Editorial: This section is being reissued in the computerized format.
9.3-14 Correction: Revision reflects the deletion of the Boron Injection Tank, as the CPSES design does not include it.
SER Section 9.3-2, page 9-16, 3rd paragraph item 1 indicates "the requirements of GDC-13 by sampling the Boron injection Tank for boron concentration". By this FSAR-CR, SER needs to be revised to reflect the deletion of Boron Injection Tank sampling.
9.3-42 thru 44 Revision: Deletes the automatic start of Reactor and 9.3-46 Make-up Water Pump, on demand from the reactor make-up controller. Reactor make-up water pumps do not
, have a safety function and run continuously in normal operation, which allows the deletion of automatic start function, l
l Table 9.3-3 Revision: Revises table to show the addition of air (Sht. 2) operated valves that isolate the steam generators during DBA'S and HELB.
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Attachment 9 to TXX-88040 January.15, 1988 Page 6 of 20 FSAR Page (as amended) Description Table 9.3-5 Revision: Revises the following as per existing design of the liquid storage tanks:
(Sheet 2 of 4) 1. Typographical error - Corrects the tank capacity to 4100 gallons which is equivalent to 550-cu. ft.
- 2. Corrects FDT to Wilt overflow from waste eva) orator condensate tank drains in Waste Hold-up Tan c (WHT).
- 3. Adds local level indication (PDP) for reactor make-up water storage tank.
(Sheet 3 of 4) 1. Corrects "overflow" to "relief valve discharge" to FDT, for Steam Generator Blowdown Spent Resin Storage Tank.
- 2. Deletes Waste Evaporator Condensate Tank - duplicate item from sheet 2 of 4.
- 3. Deletes Floor Crain Monitor Tank - duplicate item, see Waste Monitor Tank on sheet 2 of 4.
- 4. Corrects typographical error for reverse osmosis '
concentrate tanks elevation - change to 790 ft 6 in.
Section 9.4 Editorial: This section is being reissued in the computerized fonnat.
9.4-2 Clarification: Revises text to clarify the control room location and the design parameters for the systems serving the control room area.
9.4-3 Addition: Adds the function of the non-safety related air-conditioning units servicing control room areas.
9.4-6 Clarification: The intent of "at all times" for the control room air-conditioning system is clarified to be
, during nonnal operation.
I 9.4-8 Revision: Changes the operator action time to one hour to stop one pressurization and one filtration unit fan instead of eight hours.
, 9.4-10 and Editorial: Corrects the table references in the 9.4-11 paragraphs. Deletes the words, "in new conditions" to clarify the application of filter data /infonnation.
9.4-13 Clarification: This change clarifies the fuel building ,
room temperature during normal condition and adds the emergency condition room temperatures for spent fuel pool heat exchanger and pump rooms. Also, editorial changes and deletion of Table 9.4-2a. '
9.4-16 Addition: Adds an air handling unit for storage room 250A in the fuel handling building to adequately cool the non-safety related equipment.
Attachment 9 to.TXX-88040 January 15, 1988 Page 7 of 20 FSAR Page (ae amended) Description 9.4-19 Revision: Reflects the addition of "emergency fans" for room 100 to provide cooling, as per loss-of-non-safety equipment ventilation design change. Also, editorial changes and deletion of Table 9.4-2a.
9.4-19 and Clarification: This change revises the section to 9.4-21 include that a slight negative pressure 's also maintained during and after a LOCA.
9.4-21 Clarification: Adds the system name to clarify the sentence further.
Clarification: Revises to reflect that the differential measurement is provided to measure the slight negative pressure during normal operation and during, and after, a LOCA.
9.4-28 Editorial: Editorial changes and deletion of Table 9.4-2a.
Table 9.4-2 Revision: Updates the various indoor design conditions for the various plant areas, as per the present plant design.
Table 9.4-2a Revision: Deletes this table as the revised Table 9.4-2 incorporates the intent of the old Table 9.4-2a.
Table 9.4-4 Revision: Updates the design parameters for the (Shts. I and 2) Prefilter and llEPA filters to conform with vendor data.
These changes are consistent with the NRC Regulatory Guide 1.52, Rev. 1.
(Sht. 2) Revision: Updates the design parameters based on the total iodine inventory in lieu of total flow. Minimum charcoal weight is replaced with maximum iodine loading.
These changes are consistent with the NRC. Regulatory Guide 1.52, Rev. 1, Subsection C.3.i.
Table 9.4-5 Editorial: Adds degree symbols for temperatures.
(Sht. 1)
Clarification: Adds "(average)" after tempsrature for Neutron Detector Wall Unit Data.
(Sht. 2) Editorial: Adds missing degree symbols.
Addition: Provides two new entries under Control Rod Shroud Ventilation Unit Data- Type of Coil and Cooling Medium.
to TXX-88040 January 15, 1988 Page 8 of 20 FSAR Page (as amended) Description Table 9.4-5 Correction: Changes the Control Rod Shroud Ventilation (Sht. 2) Fan capacity from 62,100 to 60,000 cu f t/ minute per f an unit.
Table 9.4-6 Revision reflects the following changes:
- 1. Adds air flows based on System design.
- 2. Updates residence time for 4" bed thickness which meets the requirements 0.25 sec for 2" bed of NRC Regulatory guide 1.52.
- 3. Updates the temperature (inlet) through systeni, based on loss of ventilation calculations.
- 4. Updates the humidity through the system based on NRC R. G. 1.52.
Section 9.4A Editori91: This section is being reissued in the computerized format.
9.4A-3 Revision: Changes the design pressure of the containment pressure relief system to 1.5 psig, which is consistent with the containment design pressure criteria.
Section 9.4C Editorial: This section is being reissued in the computerized format.
9.4C-1 Correction: Provides the correct function for the Diesel Generator Ventilation System. The description previously described the function of supplying combustion air but this function is accomplished by the Diesel Generator Combustion Air Intake and Exhaust System (See FSAR Section 9.5.8).
SER Section 9.4.5, page 9-27 2nd paragraph indicates, "the diesel generator building Ventilation System is to provide outside air for diesel Combustion". Due to this FSAR change the 3ER needs to be revised to delete the system function of providing outside air for diesel combustion.
Clarification: Clarifies the operation of Diesel Generator Building exhaust fans. Sufficient fans are started to ensure adequate room ventilation. The number of fans operating is limited during the winter months to prevent the room temperature from falling below the minimum design temperature.
9.4C-2 Addition: Adds the description of the isolation dampers in the MSFW piping area ventilation system, which protect the safety related equipment located in the nearby areas from the effects of MSFW pipe breaks.
Attachment 9 to TXX-88040 January 15, 1988 Page 9 of 20 FSAR Page (as amended) Description 9.4C-5 Correction: -This change correctis the hydrogen concentration level to 2% as per FSAR Section 9.5.1, design criteria DC-305, and ANSI /ANS 59.2-1985.
9.4C-6 Revision: Describes the dampers and heaters that provide make-up air and heating following a loss of Offsite Power, to maintain the Battery Room under design conditions.
9.4C-9 Revision: This change revises the indoor design conditions for the security office, deletes humidity requirement and updates temperature to represent the present as-built conditions.
Section 9.4D Editorial: This section is being reissued in the computerized format.
9.4D-2 Revision: Reflects the following changes:
- 1. Updates the design parameters of flow and velocity based on revised design documents.
- 2. Clarifies the flow through the vents based on the present design.
- 3. Adds the classification of vent stack as seismic Category II, and its effects on safety-related system in the event of failure.
Section 9.4E Editorial: This section is being reissued in the computerized format.
9.4E-1 thru Revision: Entire chilled water system (non-safety) is 9.4E-8 redesigned to provide adequate cooling to the plant non-safety related areas.
Section 9.4F Editorial: This section is being reissued in the computerized format.
i 9.4F-1 Correction: This change corrects the capacity of the j safety related chillers to 101 tons. This is consistent with the project specification and design criteria.
t 9.5-1 Editorial: Relocates the word "quickly" to clarify the statement. Changes description from "installed" to "in situ" combustibles for consistency with the Fire Hazards Analysis. The technical basis is not affected.
l 9.5-4 and Addition: Adds the definition of engineering evaluation.
l 9.5-5 This definition is provided to define the method of i demonstrating levels of fire protection commensurate with
{ the fire hazards present.
9.5-6 Editorial: Corrects "are" to "area".
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,, Attachment 9 to TXX-88040 January 15, 1988 Page 10 of 20 FSAR Page (as amended) Description 9.5-7 Editorial: Combines two sentences and deletes redundant wording.
Addition: Adds reference to engineering evaluat. ions which identify, document and justify existing conditions and configurations.
9.5-8 Correction: Changes description to refer to the Section of the FSAR which contains the detailed description of Cable Tray Suppresst'n System design densities.
Addition: Adds reference to engineering evaluations which identify, document and justify existing conditions and configurations.
9.5-10 and Clarification: Clarifies the documentation of fire 9.5-12 detectors throughout the plant in the updated FHA format.
The technical basis of the plant Fire Protection System is unaffected.
9.5-12 Clarification: Adds references to figures to reflect new Fire Protection Water Supply design.
9.5-12 and Correction: Changes the technical description of the 9.5-13 Fire Protection Water Supply System to reflect the final as-built plant Fire Protection Water Supply System design. See Justification 1.2-26.
9.5-13 Clarification: Clarifies the description of fire hydrants. The technical basis is unaffected.
9.5-14 Clarification: Deletes specific references to certain types of sprinkler heads. The reason for this change is
- that sprinkler heads are discussed in detail in paragraph 9.5.1.4(2) b.
Correction: Deletes specific water spray densities which do not accurately reflect the plant water spray densities for cable trays. This information has been moved to Section 9.5.1.6.1.b.3.c. The technical basis of the plant Fire Protection System is unaffected.
9.5-15 Clarification: Deletes the description of atmospheric cleanup units valves which could be confused with Water Spray System valves. The technical basis of the plant Fire Protection System is unaffected.
! Clarification: Clarifies the description of fixed Fire i Suppression Systems throughout the plant by deleting the word "deluge" from the term "Deluge Water Spray System".
The technical basis of the plant Fire Protection System is unaffected.
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Attachment 9 to TXX-88040 January 15, 1988 Page 11 of 20 FSAR Page (as amended) Description 9.5-15 Correction: Deletes the description of the Diesci fire Pump Room Water Spray System to agree with the plant as-built design. The technical basis of the plant Fire Protection System is unaffected.
9.5-16 Clarification: Adds the description of atmospheric cleanup units valves to distinguish from Water Spray System valves. The technical basis of the plant Fire Protection System is unaffected.
Correction: Changes the description of the Atmospheric Cleanup Unit valve operating mode to reflect the as-built design.
9.5-16 and Clarification: Clarifies the description of fixed Fire 9.5-17 Suppression Systems throughout the plant by deleting the word "deluge" from the term "Deluge Water Spray System".
The technical basis of the plant Fire Protection System is unaffected.
9.5-17 Correction: Relocates the description of the Fuel Building Railroad Bay which is no longer protected by the type of Suppression System discussed. The technical basis of the plant Fire Protection System is unaffected.
9.5-18 and Addition: Adds description of plant manual deluge 9.5-19 sprinkler systems.
9.5-19 Addition: Adds reference to engineering evaluations which identify, document and justify existing conditions and configurations.
9.5-20 Addition: Adds reference to engineering evaluations which identify, document and justify existing conditions and configurations.
9.5-21 Editorial: Editorial correction of "on" to "of".
l See Justification for pages 9.5-12 and 9.5-13 (Correction:).
9.5-22 and Correction: Changes the technical description of the 9.5-23 Fire Protection Water Supply System to reflect the final as-built plant Fire Protection Water Supply System design (See Justification for page 1.2-26).
9.5-24 Additions: Includes reference to Fire Protection Report for Administrative Cor.trols of the Fire Protection Program. This addition is in support of the deletion of Fire Protection surveillances from Technical i Specifications.
l 9.5-25 See Justification for page 9.5-20.
Attachment 9 to TXX-88040 January 15, 1988 Page 12 of 20 FSAR Page (as amended) Description 9.5-26 Clarification: Clarifies the description of the plant as-built conditions. This was made to avoid confusion regarding non-load bearing walls and ratings. The technical basis of the plant Fire Protection System is
, unaffected.
Clarification: Clarifies the description of the use of wood througho'it the plant. The technical basis of the plant fire Protection System is unaffected.
9.5-27 Addition: Adds removable concrete hatches, a feature of the CPSES fire protection system design previously not discussed. Concrete hatches have been evaluated and justified in an engineering evaluation.
9.5-28 Revision: Changes the testing requirements for certain penetration seals. All penetration seals are tested to ASTM E-119. Only electrical penetration seals are tested to IEEE 634.
Clarification: Clariiles requirements for fire door ratings per the FHA. The technical basis of the Fire Protection System is unaffected.
Clarification: Clarifies the fire rating requirements for fire dampers. The technical basis is unaffected.
9.5-30 Clarification: Provides clarification of redundant equipment and raceway separation methods. The technical basis of the Fire Protection System is unaffected.
9.5-37 Clarification: Adds "or equivalent" to clarify the requirements of the Fire Protection Engineer to agree with regulatory guidance. The technical basis of the plant Fire protection System is unaffected.
9.5-38 Clarification: Clarifies the type of suppression system utilized in the as-built installation. The technical basis is not affected.
9.5-40 Clarification: Clarifies the description of the interim fire protection water supply. The technical basis is unaffected.
, 9.5-54 See Justification for page 9.5-20.
1 9.5-55 Editorial: Corrects an incorrect reference from "20" to "19". The technical basis is unaffected.
9.5-58 Correction: Identifies that a previously submitted and accepted deviation for fire barrier rating exists, r
Attachment 9 to TXX-88040 January 15, 1988 Page 13 of 20 FSAR Page (as amended) Description
~\
9.5-58 Clarification: Clarifies the type of suppression systems utilized in the as-built installation. The technical basis is not affected.
9.5-60 Addition: Adds statement of acceptance of modifications for security purposes, from U.L. Inc.
9.5-63 Clarification: Provides a more general description of '
materials.used for construction of cable trays.
9.5-64 Correction: Adds Containment to reflect the as-built >
locations provided with Cable Tray Fire Suppression "
Systems. The technical basis is unaffected.
Correction: Changes "cold shutdown" to "safe shutdown".
This is to provide the correct shutdown reference with respect to cabling. The. technical basis is unaffected.
Correction: Deletes reference for sprinkler head l location criteria which is no longer valid. The technical basis is unaffected.
9.5-65 Addition: Adds description of internal conduit seals.
Three hour fire rated seals are provided on one or both sides of a fire barrier inside conduits depending on the size of the conduit, except as described in Section 9.5.1.6.2.
9.5-69 Clarification: Clarifies the description of fixed Fire Suppression Systems throughout the plant by deleting the
, word "deluge" from the term "Deluge Water Spray System".
The technical basis is unaffected.
9.5-72 and Revision: The AC Essential Lighting System and DC 9.5-73 Emergency Lighting System are being reclassified as non-I Class 1E is removed from the Class IE. Lighting is not a safety related function.
The AC essential lighting System is fed from safety ,
related buses. It is isolated from the Class IE power sources with two separate Class IE breakers connected in series. These breakers are coordinated with their supply breaker and will be tested periodically. The circuits are routed in conduit to provide physical and electrical independence beyond the isolation breaker. The conduit meets the separation criteria given in Section 8.3.1.4 ,
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Attachment 9'to TXX-88040 January 15, 1988 Page 14 of 20 FSAR Page (as amended) Description 9.5-72 and The DC Emergency Lighting, which was-previously fed from 9.5-73 Class 1E station batteries, will be fed from dedicated non-Class 1E batteries. These circuits are also routed in conduit to provide physical and electrical independence from Class 1E circuits. The conduit meets the separation criteria given in Section 8.3.1.4 Although Appendix A states that emergency lighting units be sealed-beam units, fixed fluorescent units, with individual 8-hour minimum battery power supplies, will also be used for certain applications, because of their superior performance. These fluorescent units are specifically permitted by Regulatory Guide 1.120, paragraph 4.e.(1).
9.5-73 Revision: Makes correction as shown for technical accuracy. Portable radios with page-party /public address as backup provide more reliable system for conununication than does the installed Sound Powered Telephone System.
Addition: Makes addition as shown for technical accuracy. Radio to radio "talk-around" is provided see Section 9.5.2.2.4 for additional desceiption of intra plant portable radios. The page-party /public address system is used as a backup in case of damage to the fixed repeater system.
Correction: Deletes unnecessary portion since the fixed satellite receivers are not used for radio "talk-around".
9.5-74 Clarification: Deletes the word "registered" to clarify the plant Fire Protection Engineer to agree with Section 9.5.1.6.1.A.1.
9.5-74 and Addition: Adds reference to the separate evacuation 9.5-75 alarm provided for audible annunciation of a fire in Control Room complex.
9.5-78 thru Correction: Changes the technical description of the 9.5-80 Fire Protection Water Supply System to reflect the final as-built plant Fire Protection Water Supply System. See Justification for page 1.2-26.
9.5-84 Clarification: Clarifies the description of fixed Fire Suppression Systems. Throughout the plant by deleting the word "deluge" from the term "Deluge Water Spray System". The technicci basis is unaffected.
, to TXX-88040 January 15, 1988 Page 15 of 20 FSAR Page
,(_a_s amended). Description 9.5-81 Clarification: Clarifies the description of the cable tray suppression system design. The technical basis is unaffected.
9.5-85 Clarification: Clarifies the description of the as-built plant Fire Suppression Systems.
Addition: Adds reference to engineering evaluations which identify, document and justify existing conditions and configurations.
9.5-88 See Justification for page 9.5-20.
9.5-90 Clarification: Clarifies the description of fixed Fire Suppression Systems throughout the plant by deleting the word "deluge" from the term "Deluge Water Spray System".
The technical basis is unaffected.
9.5-92 Clarification: Clarifies the description of portable fire extinguishers and hose station treatment during refteling. The technical basis unaffected.
9.5-93 See Justification for page 9.5-20, 9.5-94 Addition: Adds description of manual fire fighting capability in the Control Room.
9.5-100 Clarification: Clarifies the description of the plant halon systems. The technical basis is unaffected.
9.5-101 Clarification: Clarifies the description of plant computer area classification. This guideline is shown to be inapplicable by this clarification.
9.5-102 Clarification: Clarifies the description of which equipment and what type of detection is provided for the equipment.
See Justification for page 9.5-20.
9.5-104 Clarification: Clarifies the description of fixed Fire Suppression Systems throughout the plant by deleting the word "deluge" from the term "Deluge Water Spray System".
The technical basis is unaffected.
9.5-106 and Clarification: Clarifies the description of how the Fire 9.5-114 Protection Program meets the guideline.
See Justification for page 9.5-20.
Attachinent 9 to TXX-88040 January 15, 1988 Page 16 of 20-FSAR Page (as amended) Description 9.5-116 Addition: Adds the Fire Protection Program position statements on internal conduit seals.
9.5-117 Revision: The AC Essential Lighting System and DC Emergency Lighting System are reclassified as non-Class 1E. The DC Emergency Lighting System will be powered off dedicated non-Class 1E batteries (Sce Justification for pages 9.5-72 and 9.5-73). t 9.5-118 See Justification for page 9.5-78 thru 9.5-80.
9.5-122 Addition: Makes additions to paragraph 1 as shown for technical accuracy. Provides a thorough listing of the site emergency communication systems.
Clarification: Deletes portion of paragraph 2 as shown as this is described in section 9.5.2.2.3.
Clarification: Arranges paragraph 3 as shown This is an editorial change for clarity with no technical impact.
Clarification: Changes "powered" to "driven" for consistency with the gal-Tronics Vendor manual and for technical accuracy.
9.5-124 Clarification: Makes Editorial changes by replacing "ESF" with "Class 1E" and removing "four" since more than four predetennined telephone stations remain operable during a loss of normal AC power. Removes reference to 28 trunk lines since the PABX is capable of carrying more than 28 trunk lines, t Correction: Deletes reference to the use of the Sound Powered Telephone System for emergency communication.
9.5-125 Correction: Deletes description of Sound Powered Telephone System. Sound Powered Telephone System was not
! chosen as the primary cornaunications system due to system limitations. This system is not used as the primary communication system for hot or cold shutdown per CPSES abnormal conditions procedures.
Clarification: Deletes description under 9.5.2.2.4 and inserts the revised description. The revised description provides a more thorough description of the intra plant portable radio connunication system, l
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Attachment 9 to TXX-88040 January 15, 1988 Page 17 of 20 FSAR Page
-(as amended) Description 9.5-126 Editorial: Changes heading for clarification. (Relocate words "Plar,t-to-0ffsite").
Clarification: Makes addition of "VHF" for clarification. This distinguishes the intra plant radio frequencies with lower frequencies for offsite communication.
9.5-126 and Clarification: Deletes Section 9.5.2.2.7 and inserts the 9.5-127 revised description. The revised description provides a more accurate and thorough description of Plant-to-Offsite emergency telephone systems.
9.5-127 Clarification: Replaces "multi frequency audio oscillator" with "multi-tone generator" to provide consistency with the vendor manual and a more accurate description.
Clarification: Adds reference to rotating beam lights to clarify the type of visual indication provided.
9.5-128 Clarification: Replaces "Multifrequency audio oscillator" with "multi-tone generator" to provide consistency with the vendor manual. Remove reference to ESF bus and unique alarm signal for description accuracy.
9.5-128 and Clarification: Inserts reference to aage-party /public 9.5-129 address system as backup to the portaale radio system for use by plant operators during hot shutdown for technical accuracy. This revised description provides a more comprehensive description of the use of the PABX telephone and the party /public address systems.
9.5-129 Revision: Removes reference to sound powered telephone system and include reference to portable radio system.
Portable radios are now the primary communication system used during emergency conditions.
Clarification: Revises description of intra plant portable radio transmitter receiver system to provide how system is used. The portable radio system is used for communication among fire brigade members and plant operator during use of the hot shutdown panel.
l to TXX-88040 January 15, 1988 Page 18 of 20 FSAR Page (as amended) Description 9.5-132 and Clarification: Adds information and references 9.5-133 concerning the illumination level provided by the AC Essential Lighting System.
9.5-133 Revision: The AC Essential Lighting System and DC Emergency Lighting System are reclassified as non-Class 1E. The DC Emergency Lighting System will be powered off dedicated non-Class 1E batteries. Fixed fluorescent emergency lighting units will be used in certain ap lications (See Justification for pages 9.5-72 and 9.5-73 .
9.5-134 thru Addition: Adds information concerning the illumination 9.5-136 level provided by the DC Emergency Lighting System.
Revision: The AC Essential Lighting System and DC Emergency Lighting System are reclassified as non-Class 1E (See Justification for pages 9.5-72 and 9.5-73).
9.5-136 Revision: The AC Essential Lighting System and DC Emergency Lighting System are reclassified as non-Class 1E. Detailed discussion of the installation of the raceway is no longer required. Fixed fluorescent emergency lighting units will be used in certain applications. (See Justification for pages 9.5-72 and 9.5-73).
9.5-137 Revision: The AC Essential Lighting System and DC Emergency Lighting System are reclassified as non-Class 1E. Detailed discussion of the installation of the raceway is no longer required. (See Justification for pages 9.5-72 and 9.5-73).
9.5-138 Revision: The AC Essential Lighting System and DC Emergency Lighting System are reclassified as non-Class 1E. The DC Emergency Lighting System will be powered off dedicated non-Class 1E Batteries. (See Justification for pages 9.5-72 and 9.5-73).
9.5-139 Correction: Deletes the position on NRC Regulatory Guide 1.137, as it is already discussed in 1A(B).
9.5-140 Clarification: Clarifies the system description for filling, venting, draining and removing condensate from storage tanks, as per as-built conditions and in compliance with NRC Regulatory Guide 1.137 and ANSI N195.
Attachment 9 to TXX-88040 January 15, 1988 Page 19 of 20 FSAR Page (as amended) Description 9.5-141 Revision: . This change revises the description due to replacement of simplex strainers with duplex strainers.
This update in filter removal capability eliminates the cloping of filter and improves- the nailability of quaiity diesel fuel oil supoly to the diesel generators, Deletes the reference to motor driven engine pump which :
is not used for emergency mode of operation.
9.5-142 See Justification for page 9.5-141.
Revision: This change revises the fuel oil day tank capacity from 4 1/2 hours to useable capacity of 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> of continuous operation of diesel generators at rated 100's load. This exceeds the reycirements of HRC Regulatory Guide 1.137 and ANSI N195 (66 minutes of continuous operation). Deletes the tank capacity in gallons as it varies with the density of fuel oil.
9.5-146 Correction: Deletes the diesel generator fuel oil booster pump (motor driven), which is not available
- during emergency operation of the diesel generators.
9.5-148 Correction: Deletes the reference to the motor-driven jacket water pump, which is not available during emergency operation of the diesel generators.
9.5-149 See Justification for page 9.5-148.
9.5-150 Editorial: Corrects the spelling of backup.
9.5-154 Correction: Deletes the reference to motor driven lube oil pump, which is not available during emergency operation of the diesel generators.
[
9.5-155 See Justification for page 9.5-154. Updates the following sequence numbers.
9.5-156 Correction: Replaces the "vacuum pumps" to "centrifugal i blowers" for diesel generators crankcase ventilation.
This change provides positive means of forced ventilation through the diesel generator crankcase and reflects the l as-built conditions.
9.5-162 Editorial: Typographical error, changes 0040.178 to 040.128.
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Attachment 9 to TXX-88040 m January 15,~1988 Page 20 of 20 ,
FSAR Page (as amended) Description 9.5-164 Clari fication: Clarifies that the referenced portion of
- the Branch Technical position is Appendix-"A" and-corrects the title and date of the referenced document.
9.5-165 Revision: This change revise; the reference to the current edition of the IES Lirbting llandbook.
9.5-165 and Correction: Deletes reference to incorrect code year.
9.5-166 9.5-167 Addition: Adds NUREG-0700 to th- list of references.
Table 9.5-11 Editorial: Typographical error, changes transfer pur.;p "2a" to "1b".
Correction: Deletes remedial action column, as it is covered by effects on system column.
Table 9.5-12 Ccerection: Delete', reference to motor driven auxiliary jn.iet water pump, nhich is not available during emergency operation of the diesel generators.
Table 9.5-14 Correction: Deletes reference to auxiliary lube oli pump, which is not available during emergency operation of the diesel generators.
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Attachment 10 to TXX-88040 January 15, 1988 '
Page 1 of 5 I
CPSES FSAR AMENDMENT 66 DETAILED DESCRIPTION FSAR Page (as amended) ' Description 10.3-1 Correction: Updates the design parameters based on the 4
design calculations.
10.3-2 Correction: Changes the limit for RHR operation and natural cooldown to 100 psia in Lieu of 125 psia based on design documents.
10.3-6 and Correction: Adds safety-related air accumulators for 10.3-7 PORv's, as the compressed air system is non safety-related and may nots'e av.iilable. ,
Correction: Change steam pressure to 100 psia.
10.3-7 Revision: The words "an integral" were replaced by the words "a manual." This revision is part of our response to the NRC request for additional information dated February 27, 1986, which was transmitted by our letter TXX-6126, dated December 8, 1986.
10.3-8 Revision: The sentence "Each MSIV bypass valve also has a two train module, oyen, close and auto switch on the control board." has 3een deleted. it.is revision is part !
of our response to the NRC request for additional
, information dated February 27, 1986, which was transmitted by our letter TXX-6126, dated December 8, 1986.
10.3-8 and Correction: Deletes Automatic operation and testing 10.3-10 of MSIV bypass valves, as the val,es are operated manually.
10.3-10 Revision: The sentence "There is no provision for testing the bypass valves." is deleted. This revision is part of our response to the NRC request for additional information dated February 27, 1986, which was transmitted by our letter TXX-6126, dated December 8, ,
1986.
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. Attachment 10 to TXX-88040 January 15, 1988 ;
Page 2 of 5 i FSAR Page (as amended) Description 10.3-16 Revision: This change revises this section to describe the operation of the main steam isolation bypass valves :
during operations, startup, hot standby and hot shutdown.
- This revision is part of our response to the NRC request
-for~ additional information dated February 27, 1986, which '
was transmitted by our letter TXX-6126, dated December 8, '
t 1986.
e
- 10.3-17 Correction: Adds safety related accumulators to steam ,
valves for T0AFW pump to permit valve closing for containment isolation or to isolate depressurized steam generator.
4 MSIV bypass valves:
SER Page 10-4, Section 10.3.1, 2nd Para indicates, "The MSIVS and bypass valves are designed to close in 5 seconds upon receipt of MSiv closure signal". This position is revised by SSER #12, Section 10.3.1, Page 10- ,
1, and indicates, "The MSiv bypass valve actuators are replaced with manual operators". CPE submitted the impact of this change and submitted the evaluation by a letter, dated July 10, 1985. The NRC stcff review is incomplete and identified as confirmatory issue (27) in .
Section 1.8 of this Supplement (SSER #12).
Steam Generator PORV Actuators:
SER Section 10.3.1, Page 10-4, 3rd Para indicates that, "By Amendment 22 and a letter dated June 22, 1981, PORV's ,
are provided with a nitrogen accumulators...". However, subsequent to this amendment, nitrogen accumulators were
- replaced by air accumulators by Amendment 27. This FSAR-
! CR revises the section to reflect Amendment 27, and SER '
needs to reflect the air accumulators as per Amendment i 27.
4 10.4-51 Correction: Deletes discussion on CST which is discussed ;
in Section 9.4.9. Provides ful", titles for ASME Sections '
III and IV.
10.4-52 Correction: Adds the NRC Reg. Guide and ANSI Standard applicable to Condensate and Feedwater system.
10.4-54 and Editorial: Changes Condensate Clean-up System to 10.4-55 Condensate Polishing System. ;
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Attachment 10 to TXX-88040 January 15, 1988- i Page 3 of 5 .
FSAR Page (as amended) Description 10.4-56 Correction: . Adds the MSR Separator Drain Tank which provides condensate to the system.
10.4-58 Clarification: Corrects the usage of the terms "bypass" and "splitlow bypass" and clarifies the description without changing technical content.
10.4-59 and Addition: Adds Paragraph to describe the full flow 10.4-60 flushing operation, a
Editorial: Changes to correct tenninology.
10.4-51 Revision: Adds the classification of the system piping in Safeguard Building.
Editorial: Changes to correct terminology.
10.4-64 Clarification: This change corrects the tenninology usage and clarifies Annubar functiot 10.4-66 Correction: Identifies Condensor llot Well low level as an additional trip for the Condensate Pumps.
Editorial: This change corrects terminology.
10.4-67 Clarification: Identifies that transfer from the feedwater control bypass valves to the feedwater control valve is a manual junction.
10.4-70 Editorial: Adds "FLOW" to title.
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Attachment 10 to TXX-88040 January 15, 1988 Page 4 of 5 FSAR Page Jas amended) Description 10.4-71 Revision: Changes the flow split from a fixed 40:10 (40%
- 100%-load) to 90:10 at 100% and somewhat less from 50%
to 100%, to match the as built system.
SER Section 9.2.6, Page 9-14, 2nd Para, and Section _
10.4.9.1, Page 10-15,-2nd para indicates, "The CST volume for possible emergency plant shutdown is 276,000 gallons of water". By this FSAR-CR it is reduced to 270,000 gallons (by design calculation). The SER needs to be-
- revised to reflect this change.
10.4-77 Revision: Revises text to add new air operated valves HV-2397A, HV-2398A, HV-2399A and HV-2400A. Motor operated valves HV-2397, HV-2398, HV-2399 and HV-2400 previously used to isolate steam generators during DBA's and HELB are no longer used in our analysis for this function.
10.4-84 and Revision: Reflects the change > in design parameters for ,
10.4-87 the AFW components based on the design documents, certified pump curves and W-S!r 10.1; clarifies the text i description.
10.4-93 Clarification: Changes the description to clearly describe that the isolations occur upon automatic ,
initiation of the AFW System.
, 10.4-94 Correction: Adds high flow to the description of the
^
automatic trip of the flow control valves from manual to automatic pressure control to protect the pumps. The automatic trip requires low discharge pressure and high i
flow.
SER page 10-11, Section 10.4.9.1, 2nd paragraph indicates, "the AFW System design parameters". By this i FSAR-CR, the SER needs to be revised to u)date the AlW System design parameters identified in Taale 10.4-8.
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t Attachment 10 to'TXX-88040 January 15, 1988 Page 5 of 5 ,
FSAR Page (as amended) Description 10.4-94 Correction: Update the FSAR to identify that the TDAFW.
Turbine has a mechanical / hydraulic governor in lieu of an electronic governor.
10.4-99 Revision: Deletes the stainless steel lagging on the extraction steam piping and feedwater' heaters 5 and 6 within the condenser necks, to prevent damage to tube bundles in the event of the lagging tearing away. The purpose of the insulation is to reduce the heat transfer and not to protect the components from steam impingement erosion.
10.4-122 and Correction: This change corrects the error issued 10.4-124 earlier by FSAR Amendment 65. The drain pump flow rate is 225 gpm.
10.4-138 and See Justification for page 10.4-52. ;
10.4-139 Table 10.4-8 See Justification for page 10.4-84. '
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1 w 1 to TXX-88040 January 15, 1988 Page 1 of 1 CPSES FSAR AMENDMENT 66 DETAILED DESCRIPTION FSAR Page (as amended) Description Section 11.2 Editorial: This section is being reissued in the computerized format.
11.2-12 Addition: o. Resil Disposal System physical configurat.. allows for the bypassing of the Spent Resin Storage Tank (SRST) whict weuld be needed if it were secured for maintenance or repair. Currently the FSAR states that all resin h sent '.o the SRST and then directed to a disposal sys"sm. This FSAR change is needed to allow for the system flexitility that bypassicg the SRST will provide.
Section 11.3 Editorial: This section is being reissued in the computerized forc t.
11.3-10 Addition: Changes the description to allow for greater operational flexibility of the Waste Gas Processing System and provide a means of operating the system under low pressure conditions.
11.3-11 Addition: Changes the description co allow for greater Gaseous Haste Processing System flexinility ard allo.v for operation at the higher system pressures expceted with increasing plant age.
Section 11.5 Editorial: Section 11.5 is being reissued with new format for change bars and sheets renumbered, with typographical errors corrected.
11.5-2, 11.5 6, Clarification: Changes to delete items that have been 11.5-9, 11.5-10, determined to be inappropriate and to clarify design 11.5-12 thru modifications.
11.5-15, 11.5-22, 11.5-23, 11.5-26, 11.5.27, 11.5-29, 11.5-30, 11.5-37, 11.5-38, 11.5-39, and 11.5-56 Tables 11.5-1 thru Clarification: Changes for c brifications of design 11.5-3 modificatiors. .
Table 11.5-2 Clarification: Changes environmental design conditions to match specifiv:ah ens.
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Attachment 12 to TXX-88040-
-January 15, 1988 l
-Page 1 of 2 CPSES FSAR AMENDHENT 66 DETAILED DESCRIPTION FSAR Page i (as amended) Description 45 Sections 12.1 Editorial- Sectfuns issued in new computerized format.
through 12.3 .
and 12.5 Section 12.1 Editorial: Administrative change of titles and responsibilities to reflect the current Nuclear '
[
I Operations organization.
Clarification: To delineate'the equipment qualification 12.2-1 dose evaluations from the init!al shield design '
i calculations.
12.2-9 and Clarification: This text has been replaced by Insert 1, 12.2-10 which includes the updated source term information resulting from the SWEC CAP. ;
12.2-11 Clarification; This chanje clarifies the heading for Section 12.2.1.5.
12.2-12 Clarification: A change to denote initial shleiding design as opposed to all shield evaluation (i.e.,
equipment qualification). ,
12.2-17 Revision: The vent computer code used for these calculations is no longer available for use at CPSES.
12.2-19 and Revision: The ver,t computer code used for these 12.2-20 calculations is no longer available for use at CPSES.
Table 12.2-5 Correctign: Revises source strength from 7.6 x 104 to (Sht. 5) 7.6 x 103 :
Table 12.2-7 Editorial: Table is being reissued in the omputerized (Sht. 1) format and includes editorial corrections.
Tables 12.2-16, Clarification: These new tables present updated source .
thru 12.2-19B term data and bases, and 12.2-24 Fditorial: Tables are being issued in new computerized ;
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Attachment 12 to TXX-88040 ,
January 15, 1988
. - Page 2 of 2 FSAR Page (as amended) Description-12.3-47 Clarification: Airborne monitors do not control diversion valves. They only control isolation valves.
12.3-48 Clarification: Monitoring of Control Room air is '
provided by mobile monitors. Fixed airborne nonitoring ,
is provided for Control Room Intake Air.
12.3-49 and Clarification: Revised to reflect design changes and 12.3-50 delete unnecessary information.
12.3-58 C!arification: Removes reference to "calibrator box".
CPSES does not use a "calibrator box".
12.3-59 . Clarification: Deletes current accuracy statement. The overall system accuracy is required as acceotance criteria, rather than subcompon*nt accuracj.
Table 12.3-8 Clarification: Modify setpoint bases. The monitor 1 (Sht. 6) cannot differentiate between spurious safety injection or ^
steam line break and a loss of Coolant Accident (LOCA).
The HRRHs are Reg. Guide 1.97 El variables which should
- be used for detection of significant releases assessment, -
long-term surveillance, and emergency plan actuatio.i. .
Section 12.5 See Justification for Section 12.1, "Editorial:
Administrative changes....". ,
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Attachment 13 to TXX-88040 January 15, 1988 Page 1 of 1 CPSES FSAR AMENDMENT 66 DETAILED DESCRIPTION FOR THIS TRANSMITTAL, AMENDMENT CHANGES FOR THIS SECTION HAVE NOT BEEN IDENTIFIE0 l
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Attachment 14 to TXX-88040 January 15, 1988 Page 1 of 1 CPSES FSAR AMENDMENT 66 DETAILED DESCRIPTION FSAR Page (as amended) Description Table 14.2-2 Editorial: The table is reissued due 'ot the change in number of pages of the table.
(Sht. 2) See Justification for Table 14.2-2, (Shts. 61 and 62).
(Sht.29a) Revision: Revises the test method to demonstrate the performance of the ESF pump room coolers. The original test method may not have demonstrated adaquate ventilation in the ESF pump rooms because of the possibility of not acheiving design heat loads during Hot functional testing.
(Shts. 46 and 46a) Update: Replaces "incore Thermocouples Test Summary" with "Saturation Margin Monitor Test Summary" to specify required preoperational testing for added equipment.
(Sht. 57) Clarification: Rewords the objective to explicitly define the scope of vibration testing and eliminate the ambiguity previously presented.
Clarification: Clarifies the prerequisite for testing to reflect that the piping locations selected for measurement are in place before the commencement of vibration testing, ;
Clarification: Revises the Test Method and Acceptance Criteria discussion to be consistent with the acceptance J
criteria and the scope of testing specified in Section 3.98.2.
(Shts. 61 and 62) Update: Adds "Reactor Vessel Water level Indication System Test Summary" to specify required preoperational testing for the added system.
Table 14.2-3 See Justification for page 1A(B)-36.
(Shts. 1, 20, and 27)
(Sht.18) Editorial: Adds questic.) Q010.18 to margin of Test Method Section.
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Attachment 15 to TXX-88040 January 15, 1988 Page 1 of 3 CPSES FSAR AMENDMENT 66 DETAILED DESCRIPTION FSAR Page (as amended) Description Section 15.1 Editorial: This section is being reissued in the computerized format.
15.1-29 thru Revision: Changes in the source term due to the use 15.1-32 of a design basis gap activity versus a calculated gap activity. Included iodine spike analyses per Section 15.1.5 of the Standard Review Plan. Used Rev. 3 to the Westin house "Radiation Analysis Design Manual" (versus Rev. 2 .
Table 15.1-3 Revision: Deletion of realistic analysis (See Justification for pages 15.1-29 thru 15.1-32).
Table 15.1-4 Revision: Added primary coolant activities and divided the secondary side activities into their liquid and steam components. Actual activities changed due to changes in the source term (See Justification for pages 15.1-29 thru 15.1-32).
Section 15.2 Editorial: This section is being reissued in the computerized format.
15.2-29 Editorial: Changed from 15.2-19 to 15.2-13 15.2-30 Correction: Changed reference 3 to include both the Proprietary and Non-Proprietary versions of the referenced WCAP.
Section 15.4 Editorial: This section is being reissued in the computerized format.
15.4-60 thru Revision: Changes in the source term due to the use 15.4-64 of a design basis gap activity versus a calculated gap activity. Used Rev. 3 to the Westinghouse "Radiation Analysis Design Manual" (versus Rev. 2).
Table 15.4-4 Revision: Deletion of realistic analysis (See Justification for pages 15.4-60 thru 15.4-64).
Section 15.6 Editorial: This section is being reissued in the computerized fonnat.
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Attachment 15 to TXX-88040 January 15, 1988 Pag 2 2 of 3 FSAR Page >
(as amended) Description
-15.6-4 thru Revision: Changes the instrumentation used to signal 15.6-6 operators of the break. Addition of a concurrent iodine spike when performing the radiological analysis. Changes in the source term due to tha use of Rev. 3 of the Westin house "Radiation Analysis Design Manual" (versus Rev. 2 .
15.6-30 thru Revision: Changes in the source term due to the use of a 15.6-35 design basis gap activity versus a calculated gap activity and due to the use of Rev. 3 of the Westinghouse "Radiation Analysis Design Manual" (versus Rev. 2).
15.6-36 thru Revision: More conservative methods and assumptions were ,
15.6-40 used than in the previous control room dose calculation.
Specifically, a higher inleakage rate, more conservative ECCS leakage, and more conservative penetration streaming models were used. Changes in source term due to the use of Rev. 3 of the Westin '
Manual" (versus Rev. 2)ghouse "Radiation Analysis Design .
15.6-40 and Revision: The electric hydrogen recombiners are the 15.6-42 primary means of controlling post-LOCA hydrogen buildup. ,
Therefore an analysis of the radiological consequences of '
containment purging is not provided. This'is consistent with SRP Section 15.6.5, Appendix C.
Table 15.6-3 Revision: Changes the preaccident iodine spike
~
concentration in the primary coolant due to changes in the source term (See Justification for pages 15.6-30 thru r 15.6-35).
- Table 15.6-4 Revision
- Changes the iodine appearance rate to the reactor coolant af ter the accident due to changes in the source tenn (See Justification for pages 15.6-30 thru 15.6-35).
1 Table 15.6-8 Revision: Changes the source tenn. (See Justification for pages 15.6-30 thru 15.6-35) .
i l Table 15.6-9 Revision: Deletes the realistic analysis (See l Justification for pages 15.6-30 thru 15.6-35).
Table 15.6-10 Revision: Changed the table to reflect the activity t
, available for release via ESF components following the accident. This information is more meaningful to the ,
radiological consequences of the accident than actual leakage rate.
Table 15.6-11 Deleted: Information incorporated in Table 15.6-10.
Section 15.7 Editorial: This section is being reissued in the computerized format.
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- Attachment-15 to TXX-88040 January 15, 1988 Page 3 of 3 FSAR Page i (as amended) Description j 15.7-5 See Justification for pages 15.6-30 thru 15.6-35 15.7-5, 15.7-6, Revision:- Accident was reanalyzed using an irradiated :
and 15.7-8 thru fuel assembly that had decayed for 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, per 15.7-12 Regulatory Guide 1.25. Used Rev. 3 to the Westinghouse "Radiation Analysis Design Manual" (versus Rev. 2).
Table 15.7-1 Revision: Deletion of realistic analysis (See Justification for pages 15.7-5 thru 15.7-12).
Table 15.7-3 Revision: Changes in the source term. (See Justification for page 15.6-30 thru 15.6-35).
Table 15.7-4 Revision: Deletion of realistic analysis (See Justification for page 15.6-30 thru 15.6-35).
Table 15.7-6 Revision: Table was revised to accurately reflect the noble gas and iodine activities that are released to the environment as a result of a fuel handling accident.
Table 15.7-7 See Justification for Table 15.7-1, 158-1 thru Revision: Reflects changes in the methodology used to 158-10 calculate the radiological consequences due to the accidents described in Chapter 15. A section was added to describe the computer codes used with the methodology.
Source term changes due to the use of the Rev. 3 of the Westinghouse "Radiation Analysis Design Manual."
Table 15B-1 Revision: Added additional data on the dose conversion factor. Isotopic data changes were due to changes in the source term (See Jus!.ification for pages 158-1 thru 15B-10).
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Attachment"16 to TXX-88040 , !
January 15, 1988 l
-Page 1 of 1 !
DETAILED DESCRIPTION i
FOR THIS TRANSMITTAL, A.MENDMENT CHANGES FOR THIS SECTION ' .
HAVE NOT BEEN IDENTIFIED :
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-Attachment.17 to TXX-88040 __
January- 15, 1988 ,
Page 1 of 6 CPSES FSAR AMEN 0 MENT 66 DETAILED DESCRIPTION FSAR Page (as amended) Description 17.1-29 Correction: This change is to correct the name of the Bureau of Standards. The "U.S. Bureau of Standards" is now known as the "National Bureau of Standards."
Appendix 17A Editorial: Appendix 17A is being reissued with new format for change bars, sheet renumbered, and typographical errors corrected.
17A-6 See Justification for page 3.2-5.
I Table 17A-1 Editorial: Table 17A-1 is beir.g reissued because of shifts in the text which resulted from changes to the table and typographical errors corrected.
(Sht. 1) Editorial: This change corrects the typographical error regarding the PORV Accumlator Code Class.
(Sht. 10) Revision: Added Air Accumulator Tank to air operated control valve.
Revision: A revision to reflect the replacement of expansion joints with a hard pipe based on stress analysis results.
(Sht. 14) Correction: This Table is being corrected by deleting the incorrect "Expansion Joints (Nuclear Types 11 and 111)" information indicated on Sheet 14, item 16. The correct information is covered on Sheet 26, item 33 which is consistent with current specifications.
4 (Sht. 23) Revision: Adds the class 1E battery room unit heaters.
(Sht. 24) Revision: Adds safety related dampers, duct work, supports and emergency fans for Boron injection surge tank room (Room-100).
(Sht. 27) Correction: An update is provided to item 34, Containment Polar Crane, to provide the FSAR cross-references.
(Sht. 29) Correction: An update is provided to item 35, fuel Building Overhead Crane, to provide the FSAR cross-references.
Attachment 17 to TXX-88040 January 15, 1988 Page 2 of 6 FSAR Page
,as
( amended) Description Table 17A-1 Addition: Adds handrails in Table 17A-1. Handrails (Sht. 30) installed in seismic Category I buildings have been ,
upgraded to seismic Category 11 as per requirements of Regulatory Guide 1.29 and FSAR Section 3.78.2.8.
(Shts.31and32) Revision: The AC Essential Lighting System and DC Emergency Lighting System are reclassified as non-Class 1E. This reclassification of components is not a programmatic change in the quality control program. The reduction in commitment for this equipment is acceptable since lighting is not a safety related function and adequate separation from the Class 1E systems will be provided by the following:
- 1. The AC Essential Lighting System is isolated from the Class 1E power sources with two separate, coordinated Class 1E breakers connected in series. i These breakers are coordinated with their supply breaker and will be tested periodically. The circuits are routed in conduit to provide physical and electrical independence beyond the isolation breaker. The conduit meets the separation criteria given in Section 8.3.1.4.
- 2. The DC Emergency Lighting, which was previously fed !
from Class IE station batteries, will be fed from dedicated non-Class 1E batteries. These circuits are also routed in conduit to provide physical and ,
electrical independence from Class 1E circuits. The conduit meets the separation criteria given in Section 8.3.1.4. ,
! (Shts. 32 and 33) Clarification: These components are safety i related but have no Safety Class. Therefore, the change from "NNS" to "N/A" has no significance in relation to
- the monitors because NNS means Nuclear Non-Safety.
! Clarification: These components are safety related l however, there is no applicable code or standard related I to these monitors. The change from "IEEE-323" to "Mfrs l Stds" is consistent with Note 56 and Regulatory Guide 1.97.
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, (Sht. 33) Correction: These monitors are being deleted i
because they are not safety related (QA) components and l are just part of the systen. No Safety Class, Code or l Standard, Code Class, Seismic Category and Quality Assurance requirements are applicable.
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Attachment 17 to TXX-88040 January 15, 1988 Page 3 of 6 FSAR Page (as amended) Description Table 17A-1 Revision: Upgrade-the Control Room Ventilation (Sht.-33) Monitors from "NNS" to "1E" and from "Hfrs Stds" to "lEEE-323" based on recommendation from SWEC, to comply to GDC-19 requirements. This change provides enhancement to plant operability.
(Sht.34) Correction: Changes the applicable code or standard to reflect the as-built design basis for fire stops and fire seals. The technical basis is unaffected.
Correction: Changes the applicable code or standard to reflect the as-built design basis or fire rated cooling systems.
Addition: Adds fire rated barriers to list of fire protection system components with QA applicability to reflect as-built design basis.
Correction: Deletes note 60 the exclusion of the turbine building fire rated cooling systems is adequately addressed in Section 17.2.4.
(Sht.35) Revision: Reflects the existence of higher grade seismic Category I thermowells for ASME lil Safety Class 2 and 3 piping at CPSES. This change reflects the as built plant design.
(Sht.36) Clarification: Added note 65 to the ! & C Impulse
, Tubing, Fittings, Valves and Supports entry to clarify that this entry only applies to instruments connected to HVAC Ducts.
Correction: Changes to the Nuclear Instrument Racks (NIS) to be consistent with procurement specification.
Correction: Changes to the Hot Shut Down Panel and i
Process Instrumentation Protection Racks are to be consistent with procurement specification.
Addition: Adds the Shutdown Transfer Panel.
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. Attachment 17 to TXX-88040 January 15, 1988 ,
Page 4 of 6 ,
FSAR Page ;
(as amended) Description l
Table 17A-1 See Justification for page 3.2-5.
(Sht. 39)
(Sht.44) Editorial: Corrected the spelling of "Party" from "Part".
(Sht,45) Revision: This update affects FSAR Table 17A-1. The changes are a technical update to the engineering design i of the SFP cranes and hoists. These changes affect '
previous design descriptions which could be perceived as commitments. An update is provided for Note 53 to clarify the seismic Category I classification for cranes and hoists. For seismic Category I cranes and hoists, the capability to retain control of the lifted load is indicated.
Also, an update is provided to reflect that Seismic Category I cranes and hoists will maintain their structural integrity during and after the SSE with lifted load, except for the polar crane, which is qualified for OBE with lifted. load and SSE without lifted load. Reference is made to the low probability of SSE with lif ted load for the polar crane.
Clarification: This change clarifies that components with this note 56 require the application of IEEE-323 l and associated QA.
l The deletion of the Category 2 information is because of
- redundancy. This information is already given in FSAR J
Section 7.5.
i Correction: Adds QA requirements to note 58 for future l
- activities associated with the underground fire l l
protection water supply piping serving safety related t
areas of the plant, to ensure consistency with CPSES Fire Protection commitments.
Correction: See Justification for Table 17A-1, Sht. 34, l Deletes Note 60).
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(Sht. 46) Clarification: Note 65 has been added to clarify that various instruments are only connected to llVAC Ducts.
! Clarification: See Justification for page Table 17A-1, l Sht. 36 (Clarification:).
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Section I.C Editorial: This section is being reissued in the i computerized fonnat. .
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i Attachment 17 to TXX-88040 ;
January' 15, 1988 :
- Page 5 of 6 FSAR Page !
(as amended) Dgscription ;
L 1.C-3 and Clarificatice Adds "NUREG-660" to identify the source i 1.C-11 for cross-references to 1.C.9. t
- 11.0-4 and Revision: The source term information has been removed 11.B-5 to cvoid duplication of information in accordance with Regulatory Guide 1.70, Rev. 2.
II.B-6 Revision: First sentence changed for consistency with page !!. B-4 and the last two sentences were deleted for consistency with portions of SWEC CAP. -
3 Editorial: Changes the reference to Section 12.2 for.
source term information for consistency with changes l previously noted.
1 II.B-7 Editorial: Changes the reference to Section 12.2 for consistency with previous changes. i Clarification: Added text which clarifles the role of '
the RHRS in the equi) ment qualification dose ;
evaluations, since t1e greater the radiation doses resulting from depressurized and nondepressurized LOCA e analyses were used. The RHRS was used in models for l both LOCA conditions. ;
! 11.8-8 Revision: This change replaces this section fcr :
li clarification of the role of CVCS in the equipment ,
qualification calculations.
Clarification: Updated to reflect all sources modeled
! in the PASS, and references to the descriptions of the r
appropriate source terms are changed to Section 12.2 for l.
consistency.
11.B-8 and Revision: This section has been revised for consistency
!!.B-9 with the assumptions pertaining to the SWEC CAP. ;
Clarification: Updated to reflect methods used in the !
II.B-9 and Clarification: Text changes for clarity of this section <
11 B-10 and to note that the PASS has been added. ;
II.B-10 Clarification: Text and referencing changes to reflect SWEC CAP changes.
II.B-11, II.B-12, Clarification: Changes in methods of analysis resulted ,
11.8-16, 11.8-21 in changes in acceptable error in several analyses
, and II.B-25 thru in the elimination of the need for the hot cell.
- 11.0-28 -
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Attachment 17 to TXX-88040 January 15, 1988 Page 6 of 6 FSAR Page (as amended) Description Tables 11.B.2-1 Revision: These tables have been deleted and replaced thru 11.B.2-3 in Section 12.2 to reflect the results of the SWEC CAP and to avoid unnecessary duplication of information, in accordance with Pegulatory Guide 1.70, Rev. 2.
Section ll.K Editorial: This section is being reissued in the computerized fonnat.
II.K-11 Update: NUREG-0737, item II.K.3.9 requires elimination of the derivative action associated with the pressurizer PORV Proportional-Integral Derivative (PID) controller.
Previously, the derivative feature was described as being disabled by setting the PID controller time constant to zero seconds. This cannot be accomplished without changing the design of the PID controller card.
The normal method for disabling the derivative action of this type of PID controller is to remove the jumpers that tie the derivative circuits to the signal flow path. This method was in fact used to modify the existing PORV PID controller card.
This change affects the CPSES SER (7/81) writeup for item II.K.3.9 (P.22-76). Since the alternate method used does in fact removed the derivative action from the PORV controller the intent of NVREG-0737 Item !!.K.3.9 is maintained.
Section 111.0 Editorial: This section is being reissued in the computerized format.
111.0-6 Clarification: Modify the requirement that all silver zeolite cartridges used for grab sampling during accident conditions surveyed and counted LAW applicable Emergency Plan Procedure.
Attachment 18 to TXX-88040 January 15, 1988 Page 1 of 7 CPSES FSAR AMENDMENT 66 DETAILED DESCRIPTION 3 FSAR Page (as amended) Description
! 010-33 Editorial: Changes the word "at" to "as".
010-47 Clarification: The inclusion of "Fire Safe" identifies the type of shutdown path being analyzed.
Correction: Deletes the detailed descriptions of the requirements for fire rated barriers in this section.
This information is discussed in depth in section 9.5.1.6,0.1.j of the FSAR which correctly reflects how rated fire barriers are employed.
010-50 Update: Reflects the completion of the breaker / fuse coordination analysis.
Clarification: Clarifies the requirements for coordination and more clearly specifies the circuits of i Concern.
010-50 and Update: Revises the methodology for reviewing cables 010-51 for common enclosure concerns. A complete analysis was performed in lieu of a sampling method.
010-52 Addition: Adds the separation criteria of "fire safe shutdown" cables and equipment and "fire stops" as part of the fire propagation / mitigation scheme. Adds ,
reference to Section 9.5.1.5.5. These additions reflect how intervening combustibles are addressed in the Fire Safe Shutdown Analysis.
010-53 Editorial: Adds the word "system" after "high/ low pressure."
Clarification: Adds the word "potential" before the word "spurious" to more properly describe the type of
{ problem being considered.
- Clarification
- Changes the words "actions" to actuations" to distinguish this type of problem from .
, operator action which is addressed separately.
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Attachment 18 to TXX-88040 January 15, 1988 Page 2 of 7 FSAR Page (as amended) Description .
0:0-53 Correction: Changes the word "designated" to "required" and adds the word "fire " to describe the type of safe shutdown being considers. This does not change the design criteria or basis. ,
010-54 Clarification: Changes the description of the redundant train to "fire safe shutdown," which only considers '
equipment required for fire and is a subset of the redundant safety trains.
Correction: Deletes requirement that a redundant component be assigned to a different safety train.
Redundant components may also be supplied from the same train. This does not change the design criteria or basis, i
Revision: Adds the consideration of alternate shutdown capability when offsite power is assumed to be available, which is a necessary condition with or without the availability of off-site power.
010-59 Update: Reflects the completion of the breaker / fuse I coordination study and indicates that the Fire Safe
. Shutdown Analysis addresses these conditions as associated circuits as required.
010-62 Revision: Changes hot shutdown to hot standby. This
, change was made in order to consistently reflect and correctly use these definitions as used in both the Fire Safe Shutdown Analysis and the Technical Specifications.
010-63 Clarification: Adds "potential" to identify the ty)es i of spurious operation. This is added to distinguisi the
- host of "potential" fire induced spurious operations due
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to a fire, from "actual" spurious operations which are addressed separately as single or random failures, etc.
It is it.portant to stress that all the spurious .
operations being discussed due to a fire are only a i "potential" problem.
Update: Deletes reference to Table 4-1.4 from the !
i superseded FPPR by the Fire Protection Report, which ,
indicates that this is available in other site !
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Attachment 18 to TXX-88040 January 15, 1988 Page 3 of 7 FSAR Page '
(as amended) Description 010-64 Editorial: Replaces "STP" with "Shutdown Transfer Panel (STP).
Clarification: Specifies the applicability of CPSES ;
Procedure ABN-803A and required operator actions for safe shutdown.
Addition: Added statement to verify required post fire operator actions for other fire areas exist in plant procedures.
Editorial: Deletes all references to tables in the FPPR, because the FPPR has been su)ersceded by the FPR and this information is now availa)le in other site documents.
010-66 Addition: The contents of R010.34 was discussed with the NRC during a meeting on November 12, 1987, The r Standard Review Plan (SRP) requirement to analyze the jet impingement effects of a one square foot arbitrary J break in superpipe areas is being deleted from the SRP.
In place of this requirement is a cautionary note to avoid concentrating essential cables in these areas.
Our response states that the essential cable concentration in these areas is low and therefore meets the guidelines of this cautionary note.
022-28 Addition: Adds reference to Section 6.2.6 in response a.
Correction: Corrects referenced section in response b.
Addition: Adds reference to Figure 8.3-16 in response c.
Addition: Adds reference to Table 6.2.4-5 in response d.
022-28 and Clarification: All the penetrations that utilize 022-29 expansion bellows are able to be tested at Pa by design. However, some of these penetration bellows have been made exempt from testing because they are no longer .
part of the containment pressure boundary. The section references have been supplied to clarify where the actual testing requirements are shown. See also Q&R
- 22.19d.
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Attachment 18 to TXX-88040 '
January 15, 1988 Page 5 of 7 FSAR Page (as amended) Description 040-18 Clarification: Reflects that the Diesel Generator Power window on the Safety System Inoperable Indication panel is activated by those conditions that render the Diesel Generator inoperable for auto start during emergency ,
conditions instead of the SS!! system performing this function.
040.20 Revision: The motor driven and turbine driven auxiliary feedwater pump low suction pressure interlocks were disabled. During emergency conditions it is important to have the AFW pump available. Thus, disabling these interlocks ensures that they will not preclude the :
automatic operation of the AFW pump.
Clarification: Deleted reference to the lube oil system safety related motor pump setes. This system is not interlocked and therefore should not be referenced in -
this section.
040-35 Correction: Add ' Response to 0040.112', as this is applicable to response to Q040.24.
SER IMPACTS:
i (1) SER Section 9.5.4.2, page 9-39, 2nd paragraph indicates," day tank capacity 2160 gallons l sufficent to power the diesel engine at rated load for 41/2 hour". By this FSAR-CR, SER needs to be revised to say day tank usuable capacity sufficent
- to power the diesel engine at rated load for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
(2) SER Section 9.5.5, page 9-40, paragraph 6 indicates, "motor driven auxilary pump for jacket water is available for continuos water circulation, in the event of engine-driven pump fall." By this FSAR-CR," SER needs to be revised to indicate that motor-driven auxiliary jacket water pump is not ,
available during emergency conditions, llowever in
, this scenario, backup diesel generator set is i available.
(3) SER Section 9.5.7, page 9-43, paragraph 2 indicates, the system has an motor-driven lube oil pump available in the event of failure of engine
.I driven pump. By this FSAR-CR SER needs to be revised to indicate that the motor-driven lube oil pump is not available as a backup to engine driven lube oil pump. However, in this scenario, backup i diesel generator jet pump is available. ,
8 to TXX-88040 January 15, 1988 Page 4 of 7 FSAR Page (as amended) Description 022-31 Revision: Changes the description to match post-TMI design changes. The plant vent stack particulate, iodine and gaseous monitor is not required to close the containment pressure relief isolation valves as previously stated.
022-47 Revision: Provides additional detail for water filled penetrations. See justification of page 6.2-127.
022-48 Clarification: Item R022.19d has been revised to match page 022-29. The same question requires the same response.
Revision: Item R022.199 has been revised to include all containment penetrations which are exempt from Type C testing. The specific valves exempt from Type C testing are shown on Table 6.2.4-2, whereas general guidance is provided as shown 022-52 Clarification: Adds how leak rate testing of vent isolation valves will be accomplished during plant surveillance tests.
Tables 032.110-1 Update: These changes to the text and tables have been thru 032.110-6 made to correct errors of inclusion, omission and applicability based upon, Reg. Guide 1.97, Rev. 2, the as-built plant design, the SER and supplements and the post THI requirements. In addition, additional information (i.e., notes and deviations) have been provided where there is ambiguity in the requirements, to clarify CPSES position.
Attachment 18 to TXX-88040 January 15, 1988 Page 6 of 7 t FSAR Page (as amended) Description SEP IMPACTS:
f (1) SER Section 9.5.4.2, page 9-39, paragraph 2 040-72 thru Revision: Revises response to reflect the new startup 1
040-72b transfonner installation. (Seegeneraldiscussionunder Section 8 for details).
The design modification has improved the voltages i available at the safety related buses. Based on the preliminary (non-validated) calculations, the minimum and maximum voltages at the safety related buses will :
ensure adeqt, ate voltages at all safety related l equipment. When the voltage profile calculations are finalized, a revised response will be provided. ;
There are now no specific dynamic design features in the plant electrical system to assure that acceptable voltage levels are maintained at the safety related buses, i
040-168 Revision: Changes are as follows: !
040-169 and Revision: 1) fuel oil will be sampled before transfer i 040-170 to stora i page IA(ge B)-76tank and end
& 77), tested before viscosity
- 2) delete 30 days (see item test as it 4 on i
is covered under ASTM D975-1981 (see item 4 on page 1A(B)-76 & 77). ,
SER IMPACTS:
SER Section 9.5.4.2, page 9-39, paragraph 4 indicates, ;
, "The fuel oil storage and transfer system piping and ;
components are designed to seismic category I, ASME ;
! Section III, Class 3 (Quality Class C). By this FSAR '
I change request, SER need to revise for venting !
components which are seismically supported, but not ASME i Section III, Class 3. Missle protection is provided for vent paths.
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I Attachment 18 to TXX-88040
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January 15, 1988 Page 7 of 7 -;
t FSAR Page !
(as amended) Description ;
SER IMPACTS:
040-169 and SER Section 9.5.4.2, page 9-39, paragraph 5 indicates, 040-170 "The design of emergency diesel engine fuel oil storage l and transfer system conforms to Regulatory Guide 1.137." ,
SER needs to clarify for.the exceptions to R.G.1.137 by -
4 this FSAR-CR.
112-3a Revision: Deletes previous response to item b and references Section 6.6.8.
a 112-14 Update: Incorporation of Table 3.9N-21, which is a
, sununary of maximum stresses in the Reactor Ccolant loop
- Piping to complete our conunitment provided in Response '
to NRC question Qll2.14. t 210-13 Revision: Revises response to Q210.9'to delete the I requirement to supply additional information related to Arbitrary Intermediate Breaks. Generic Letter 87-11 eleminates the need to postulate these breaks.
210-14 Revision: Revises response to Q210.10 per Generic Letter 87-11. l 212-198 Revision: Updated the response to be consistent with l the change made in Section 15.1.3 and Tables 15.1-4 and !
l 15.1-3. !
a 220-2 Clarification: References Section 4.4.6.4 for !
! description.
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! 372-14 Clarification: 1he meteoroligical system was modified 1 per Regulatory Guide 1.23 (Proposed Rev.1). The j temperature redundent measurement at the primary i meteorological tower is now obtained from sensors at 10 ;
j and 60 meters.
- 372-54 and See justification for page 372-14.
j 372-55 5 421-13 Update: Substitutes "Executive Vice President Nuclear ,
3' Engineering and Operations" for "Ececutive Vice l President and General Manager of TUGC0", corrects the title of the Director, Quality Assurance (his title was previously the Manager, Quality Assurance).
421-19 See justification for page 421-13. ;
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441-11 Clarification: Correct FSAR subsection references. L f
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. . . , - . -. . . . .- - . ~ , .-
Attachment 19'to TXX-88040.
January 15,-1988 Page 1 of 4 CPSES FSAR AMENDMENT 66 DETAILED DESCRIPTION FSAR Page (as amended) Description Figure 2.3-12 Clarification: ' Corrects the location-of the primary
, meteorological tower to be consistant with the FSAR Figure 2.1-2 series and Technical Specification Figare 5.1-1.
Figure 3.68-11 Revision: These figures provide the latest bre.ak thru 3.68-14, locations postulated in occordance with the requirements 3.68-19 thru of FSAR Section 3.68. These figures omit stress tables 3.6B-22, :,.68-23-3, previous provided since this analysis information is 3.68-24-1 thru maintained by System Interaction Program "Calculation 3.68-24-4, 3.68-25-1 Books".
thru 3.68-25-4, 3.68-31-1, 3.6R-31-2, 3.68-32, 3.68-3 thru 3.68-38, 3.68-39-1, 3.6B-39-2, 3.68 a0, 3.68-41, 3.68-43, 3.68-44, 3.6B-45, 3.68-48-1, 3.68-48-2, 3.6B-49.
3.68-50-1, 3.6B-50-2, 3.68-51-1, 3.6B-51-2, 3.68-52 thru 3.6B-ES, 3.68-57-1 .68-57-2, 3.68-58-1 saru 3.68-58-3, 3.68-59-1, 3.68-59-2, 3.6B-60, 3.68-61-1, 3.6B-61-2, 3.68-62, 3.68-63, 3.6B-64-1, 3.68-64-2, 3.6B-65, 3.68-66-1, 3.68-66-2, 3.68-67-1
. thru 3.68-67-3, 3.68-68-1, 3.68-68-2, 3.6B-69 thru 3.69-72, 3.6B-73-1, 3.68-73-2, 3.68-74, 3.68-75, 3.68-78 thru 3.68-81, 3.6B-82-1, 3.68-82-2, 3.6B-82-3, 3.68-83, 3.6B-84, 3.68-86, 3.6B-87-1 and 3.68-88-1 I
- - . 9 of TXX-88040 January 15, 1988 Page 2 of 4 FSAR Page.
(as amended) Description Figures 3.6B-89 Clarification: Revises Note 2 by replacing the words thru 3.68 "may be elir..inated" with "are not required." Although the loop restraints and non-crushable are .wt required, not all are being eliminated.
Figures 3.68-93-1, Revision: This change is made to reflect the revised 3.68-93-2, 3.68-94 environmental model utilized in the current environmental and 3.68-95 analysis.
Figure 3.8-8 Rev sion: Adds the containment expansion joint to i
reflect the as-built condition. This is consistent with FSAR Figure 6.2.6-1.
Figure 5.4-16 Revision: Deletes figure because the crossover leg restraints are functionally removed from the design.
Figure 5.4-17 Revision: Deletes figure because the crossover Leg vertical run restraints are functionally removed from the design.
Figure 5.4-18 Revision: Deletes figure because the hot leg restraint is functionally removed ' rom the design.
Figure 6.2.4-1 (Sht. 1) Revision: Modifies valve arranaement 4 to add thermal eliet valve.
(Sht. 2) itevision: Modifies valve arrangement 5 to add thermal relief valve.
(Sht. 4) Correction: Corrects symbol indica q for locked closed valve.
(Sht. 5) Revision: Adds containment isolation valves to valve arrangement 17 which were previously ommitted from this Figure.
(Sht. 6) Revision: Modifies valve arrangement 22 to add thermal relief valve.
(Sht. 7) Revision: Modifies valve arrangements 25, 26, 27, and 28 to add thermal relief valves.
(Sht.8) Revision: Modifies valve arrangeent 30 to add thermal relief valve.
(%t. 9) Revision: Deletes manual isolation valve from valve arrangement 36.
Attachment 19 of TXX-88040 January 15, 1988 Page 3 of 4 FSAR Page (as amended) Description Figure 7.1-3 Update: Revises location of Class 1E and accident (Shts. I thru 22) monitoring instrumants.
(Shts. 23 thru 36) Revision: These pages have been deleted but are reserved for Unit 2_ instrumentation locations.
Figures 8.2-1 thru Revision: Revises figures to show the new 8.2-4, 8.2-5 startup transformer installation. (Seegeneral (Shts. 1 and 2), discussion for Sections 8.1, 8.2 and 8.3).
8.2-6, and 8.2-8 (Shts. 1 and 2)
Figures 8.2-5 and 8.2-8 have been split into two sheets to correspond to the computer aided design (CAD) drawings now used at the project site.
Figure 0.3-16 Revision: Revises figure to reflect changes made during the replacement of the electric penetration modules and the as-built configuration of the plant.
Figures 8.3-18 Revision: Figures 8.3-18 through 8.3-45 are being thru 8.3-45 deleted. The adaquacy of penetration protection devices (1 Sheet) to protect the penetrations is established by detailed calculations. These calculations compare the time current characteristics of protected devices against penetration compatibility curves. These calculations are
, available at the site. The time current characteristics curves represent highly detailed design information which is not required to be in the FSAR.
Figure 9.1-6 See Justification for Figure 3.8-8.
Figures 9.4-1 Revision: Revises the flow diagram to reflect the (Shts. I thru 3), as-built design. Deletes the fire dampers. Updates 9.4-3, 9.4-4 the air flow and ch?.ges the layout of the flow (Shts. 1 and 2)c diagrams. Adds cooling coi,s to CRDM (Figure 9.4-5).
9.4-5, 9.4-7, 9.4-12, 9.4-14 and 9.4-15 Figure 9.4-2 Revision: Revises the figures to reflect 6sbuilt (Shts. I thru 3) conditions and the addition of cooling to boron injection surge tank room (Room 100) per changes identified in Section 9.4.3.1.
(Sht. 3) Addition: Adds an air handling unit in storage room 250A.
Figure 9.4-6 Revision: Revises the figure to reflect the containment penetrations piping test connections as locked closed per GDC-56 (10CFR 50 Appendix-A). Also clarifies the note.
Attachment 19 of TXX-88040 January 15, 1988 Page 4 of 4 FSAR Page (as amended) Description Figure 9.4-8 Revision: Revises the figure to reflect the battery room ;
desig per changes identified for page 9.4C-6.
Figure 9.4-9 Revision: Revises the figure to reflect the flow and l velocity through the plant vent stack per changes identified for p6ge 9.4D-2.
L Figure 9.4-11 Revision: Revises the figures to reflect the changes due (Shts. I thru 4) to system design as identified for pages 9.4E-1 through 9.4E-8.
(Sht. 2) Revision: Adds relief valves and "locked closed" to valves.
Figure 9.5-43 Correction: Changes the title of the figure to reflect the status of the illustrated water supply system. This system is now the interim fire protection water supply.
Figured 9.5-44 Clarification: Title blocks are redrawn and figures thru 9.5-47 reissued to enhance legibility.
Figure 9.5-48 Correction: Modifies figure to show normally closed manual isolation valves in the containment penetration boundry. These valves must be locked closed per GDC 56.
Also, illustrates safety class break in the penetration boundary at the isolation valve.
Figures 9.5-61 Addition: Adds figures to illustrate details of the and 9.5-62 fire protection water supply design to supplement the I
description of the new system provided.
Figure 11.5-1 Revision: Revises figure to add Control Room CRT and includes an editorial change to the legend.
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