View source for B12246, Forwards Reviews of Isap 1.14.2, Install New 480-Volt Load Ctr & Rearrange Equipment in Fire Area S-8, 1.14.4, Install Remote Shutdown Instrumentation Panel & 1.61, Pressurized Thermal Shock, Per 850517 Commitment

{{Adams
| number = ML20215J034
| issue date = 10/16/1986
| title = Forwards Reviews of Isap 1.14.2, Install New 480-Volt Load Ctr & Rearrange Equipment in Fire Area S-8, 1.14.4, Install Remote Shutdown Instrumentation Panel & 1.61, Pressurized Thermal Shock, Per 850517 Commitment
| author name = Opeka J
| author affiliation = CONNECTICUT YANKEE ATOMIC POWER CO.
| addressee name = Grimes C
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000213
| license number = 
| contact person = 
| case reference number = REF-GTECI-A-49, REF-GTECI-RV, TASK-A-49, TASK-OR
| document report number = B12246, NUDOCS 8610240267
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 10
}}

=Text=
{{#Wiki_filter:* e CONNECTICUT YANKEE ATOMIC POWER COMPANY B E R L I N. CONNECTICUT P o BOX 270  HARTFORD. CONNECTICUT 06141-0270 TELEPHONE 203-665-5000 October 16,1986 Docket No. 50-213 B12246 Office of Nuclear Reactor Regulation Attn: Mr. Christopher 1. Grimes, Director Integrated Safety Assessment Project Directorate Division of PWR Licensing - B U.S. Nuclear Regulatory Commission Washington, D.C. 20555

==References:==
(1)  3. F. Opeka letter to C.1. Grimes, dated May 17, 1985.
(2)  H. L. Thompson letter to J. F. Opeka, dated July 31,1985.
Gentlemen:
Haddam Neck Plant Integrated Safety Assessment Program In Reference (1), Connecticut Yankee Atomic Power Company (CYAPCO) provided a proposed scope for the Integrated Safety Assessment Program (ISAP) review of the Haddam Neck Plant. In Reference (2), the Staff formally issued the results of the ISAP screening review process, establishing the scope of ISAP for Haddam Neck and initiating issue-specific evaluations. Reference (1) also indicated that for each issue or topic included in ISAP, CYAPCO would provide a discussion of the safety objective and an evaluation of the plant design with respect to the issue being addressed to identify specific items to be considered in the integrated asse:,sment. In accordance with this commitment, reviews for the following ISAP topics are attached:
: 1)    ISAP Topic No.1.14.2 " Install New 430V Load Center and Rearrange Equipment in Fire Area S-8"
: 2)    ISAP Topic No. 1.14.4 - " Install Remote Shutdown Instrumentation Panel"
: 3)    ISAP Topic No.1.61 " Pressurized Thermal Shock" If you have any questions concerning the attached reviews, please contact us.
Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY 8610240267 861016 3 PDR F
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J. F. Op6ka       V Senior Vice President                                       hoh  g
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Haddam. Neck ISAP Topic No.1.14.2 Install New 480V Load Center and Rearrange Equipment in Fire Area S-8 i
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Haddam Neck ISAP Topic No.1.14.2                                            .
Install New 480V Load Center and Rearrange Equipment In Fire Area S-S I.      Introduction This topic is the result of CYAPCO's efforts regarding the requirements of the Fire Protection Rule,10CFR50.48 and Appendix R to 10CFR50.
The proposed modifications in this subtopic are necessary to demonstrate compliance with Appendix R criteria. These include the installation of a new 480 volt motor control center, a new battery charger, a new DC bus,
;                        relocation of two vital AC station inverters, and installation of a new 480V load center. The preceding modifications are a part of our commitment to the new switchgear room design.
II. Review Criteria
: 1.            10CFR50, Appendix R                " Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1,1979" III. Related Topics / Interfaces
: 1.           ISAP Topic No.1.14 " Appendix R Modifications"
: 2.           ISAP Topic No.1.14.1 " Curbs, Ramps, Water Control Structures, Seals and Shields" 4                        3.           ISAP Topic No. 1.14.3                " Appendix R Related Control Circuit Modifications" j                        4.           ISAP Topic No.1.14.4 " Remote Shutdown Instrumentation Panel"
 ;                       5.           ISAP Topic No.1.14.5 " Fire Protection Improvement Area S-1"
: 6.           ISAP Topic No.1.14.6 " Installation of Fire Damper to Separate Charging Pumps" IV. Evaluation The existing switchgear room DC system will be modified as follows:
: 1.           The existing spare battery located in the south corner of the room will be designated as Battery "C". A new "C" battery charger and 125V DC Bus 3 will be installed with manual tie capability to 125V DC Bus 1 and 2.
: 2.           The existing Battery "B" will be redesignated as Battery "A" and connected to 125V DC Bus 1.
: 3.           The existing Battery "A" will be moved to the new switchgear room i
and redesignated Battery "B". A new "B" battery charger and 125V DC Bus 2A will be installed with connection to 125V DC Bus 2.
The following components will be installed in the new switchgear room:
: 1.           A new safety-related 1500/2000 kVA XFMR-480 volt load center. It will be powered from the 4160V Emergency Bus 9, via a new Breaker Compartment located in the Diesel Generator Building.
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: 2. A new safety-related 480 volt motor control center.
: 3. One set of relocated station batteries, one new battery charger and one new DC Bus.
: 4. Two new station inverter vital power supplies.
: 5. Remote instrumentation panel.
V. Conclusions The above-mentioned modifications are scheduled to be fully implemented in the 1989 refueling outage at Haddam Neck. Based on our commitment to Appendix R compliance, these items will be further addressed in the integrated assessment.
VI. References
'j             1. W. G. Counsil letter to D. G. Eisenhut     "Haddam Neck Plant Fire Protection", dated March 1,1982,
: 2. W. G. Counsil letter to D. M. Crutchfield "Haddam Neck Plant Clarifications of Appendix R Reviews," dated July 30,1982.
: 3. W. G. Counsil letter to D. G. Eisenhut " Fire Protection Appendix R Review - Haddam Neck Plant", dated December 15,1982.
: 4. 3. F. Opeka' letter to H. L. Thompson            "Haddam Neck Fire Protection", dated September 16,1985.
: 3. F. Opeka letter to C. I. Grimes, "Haddam Neck Plant - Fire
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Protection Schedular Exemption," dated March 7,1986.
: 6. F. M. Akstulewicz letter to 3. F. Opeka " Summary of April 1,1986 Meeting with Utility Representatives Concerning the Pending Fire Protection Schedular Exemption for the Switchgear Room," dated April 11,1986.
: 7. 3. F. Opeka letter to C. I. Grimes, "Haddam Neck Plant, Conceptual Design of the New Switchgear Room," dated June 30,1986.
: 8. H. R. Denton letter to 3. F. Opeka, "Haddam Neck Plant - Schedular Exemption," dated August 25,1986.

Docket No. 50-213 B12246 Haddam Neck ISAP Topic No.1.14.4 Install Remote Shutdown Instrumentation Panel i
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Haddam Neck ISAP Topic No.1.14.4 Install Remote Shutdown Instrumentation Panel
;                         I. Introduction i
This topic is the result of CYAPCO's efforts regarding the requirements of the Fire Protection Rule,10CFR50.48 and Appendix R to 10CFR50.
 ,                            The proposed modifications in this subtopic are necessary to demonstrate compliance with Appendix R criteria. These include the installation of a safe shutdown instrumentation panel in an area separate from the control room.
II. Review Criteria
: 1.                         10CFR50, Appendix R            " Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1,1979" l                        III. Related Topics / Interfaces
:                             1.                         ISAP Topic No.1.14 " Appendix R Modifications"
: 2.                         ISAP Topic No.1.14.1 " Curbs, Ramps, Water Control Structures, Seals and Shields"
: 3.                         ISAP Topic No.1.14.2         " Install New 480 V L/C and Rearrange Equipment in Fire Area S-8"
: 4.                         ISAP Topic No. 1.14.3             " Appendix R Related Control Circuit Modifications"
: 5.                         ISAP Topic No.1.14.5 " Fire Protection Improvement Area S-1"
: 6.                         ISAP Topic No.1.14.6 " Installation of Fire Damper to Separate
;                                                       Charging Pumps" i
IV. Evaluation This project involves the installation of a safe shutdown instrumentation panel in the new switchgear room. This panel would be used af ter a major fire in the control room and would provide operators with the following type of information.
o                         Pressurizer pressure and level.
1 o                         Steam generator pressure and level.
;                             o                         Reactor coolant system temperature.
o                         Source range neutron monitoring.
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                                                                                           -                            V.           Conclusions i                                     The proposed modifications will be implemented during the 1989 refueling outage at Haddam Neck. As a result of CYAPCO's ongoing commitment to Kppendix -R compliance, further analysis of this project- will be undertaken in the integrated assessment.
VI.'         References i
: 1.       W.' G. Counsil letter to D. G. Eisenhut                                "Haddam Neck Plant Fire Protection", dated March 1,1982.
^
: 2.       W. G. Counsil letter to D. M. Crutchfield "Haddam Neck Plant Clarifications of Appendix R Reviews," dated July 30,1982.
: 3.       W. G. Counsil letter to D. G. Eisenhut " Fire Protection Appendix R Review - Haddam Neck Plant",' dated December 15,1982.
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: 4.       3. F. Opeka letter to ~ H. L. Thompson                                     "Haddam Neck Fire Protection", dated September 16,1985.
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: 5.       3. F. Opeka letter to                     C.'     I. Grimes, "Haddam Neck Plant Fire Protection Schedular Exemption," dated March 7,1986.
:                                       6.       F. M. Akstulewicz letter to 3. F. Opeka " Summary of April 1,1986 i
Meeting 'with Utility Representatives Concerning the Pending Fire Protection Schedular Exemption for the Switchgear Room," dated April 11,1986.
: 7.        3. F. Opeka letter to C. I. Grimes, "Haddam Neck Plant, Conceptual Design of the New Switchgear Room," dated June 30,1986.                                                                                      '
  !'                                   8.        H. R. Denton letter to 3. F. Opeka, "Haddam Neck Plant -
Switchgear Room Schedular Exemption," dated August 25,1986.
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Docket No. 50-213 B12246 1
Haddam Neck ISAP Topic No.1.61 Pressurized Thermal Shock October 1986

Haddam Neck ISAP Topic No.1.61 Pressurized Thermal Shock (USI A-49)
: 1. - Introduction A severe system overcooling event fo!! owed by repressurization of the reactor vesselin which fracture toughness has been reduced due to neutron irradiation could cause an extensive propagation of crack-like defects in the vessel wall, thus compromising reactor vessel integrity. The reactor system overcooling events that can result from a variety of causes include instrumentation and control system malfunctions and postulated accidents such as small break loss-of-coolant accidents (LOCAs), main' steam line breaks (MSLBs), feedwater pipe breaks, or stuck open valves in either the primary or secondary system. Rapid cooling of the reactor vessel internal surface causes a temperature distribution across the reactor vessel wall.
The temperature distribution results in thermal stresses, the magnitude of which depends on the temperature differences across the reactor vessel wall. A maximum tensile stress occurs at the inside surface of the vessel and a compressive stress occurs at the outside surface. These stresses combine with the hoop stress caused by the internal pressure in the vessel.
As long as the fracture resistance of the reactor vessel material remains relatively high, such events will not cause failure. After the fracture toughness of the vessel is reduced by neutron irradiation, several thermal transients could cause fairly small flaws to propagate near the inner surface and result in significant cracking. The vessels of concern are those which have accumulated high neutron radiation exposure and which are made of material that has a high sensitivity to neutron irradiation (such as those made with welds of high copper content).
In order to impact the reactor vessel integrity by pressurized thermal shock (PTS) events, a number of contributing factors must be present.
These factors are: 1) a reactor vessel. flaw of correct size to propagate, 2) high copper content, 3) a relatively high level of irradiation, 4) a severe overcooling transient with repressurization, and 5) a resulting crack of such size and location that the ability of the reactor vessel to maintain core cooling is af fected.
II. Review Criteria
: 1.      10CFR50.61, " Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events"
: 2.      Generic Letter No. 81-19, " Thermal Shock to Reactor Pressure Vessels" Ill. Related Topics / Interfaces
: 1.      ISAP Topic No.1.52 " Pressure Vessel Transient Protection"
: 2.      ISAP Topic No.1.59      " Additional Low Temperature Overpressure Protection"
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IV. Evaluation 10CFR50.61 requires that licensees submit values of the reference temperature for pressurized thermal shock (RTpTS) from the time of submittal to the expiration date of the operating license. In response to these requirements, evaluations have recently been performed for the Haddam Neck Plant. Reference i forwarded to the Staff the RTPTS that has been calculated for the time of this submittal and for both the current operating license expiration date and the planned extension to the OL expiration date. Information was provided regarding core loading patterns, the source of the best estimate weight percent of copper and nickel in the vessel material, and the relationship of the material on which any measurements were made to the actual vessel material. These calculations will be updated whenever changes in core loadings, surveillance measurements or other information indicate a significant change in the RTPTS Projected values, as required by 10CFR50.61(b)(1).
CYAPCO has concluded that the values calculated for the RTPTS for the applicable locations at Haddam Neck will not exceed the screening criteria of 2700F for plates, forgings and axial weld materials, and 3000F for circumferential weld materials. Compliance with 10CFR50.61 has thereby been established.
V. Conclusions l            Pending subsequent review by the Staff, CYAPCO considers this topic to i            be adequately addressed for the Haddam Neck Plant.
VI. References
: 1.           D.G. Eisenhut letter to 3.F.Opeka, " Generic Letter 31-09, Reactor Vessel Pressurized Thermal Shock," dated April 20,1981.
: 2.          3.F. Opeka letter to C.I. Grimes, V.S. Noonan, and A.C. Thadani, l                        "10CFR50.61 Compliance," dated January 23,1986.
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