ML20141M300
| ML20141M300 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 08/06/1991 |
| From: | Skolds J SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9208110172 | |
| Download: ML20141M300 (16) | |
Text
__. - _ - _ _ _ _ _ - _ _
So th C r lin) Electric & o;s Cornp;ny J hn k: e Jrnkinsville, SC 29065 Nucleu Operabons (803) 345 4040 SCE&G August 4,1992 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20055 Gentleaer.:
Subject:
VIRGIL C. SUMMER NUCLEAR STATION (VCSNS)
DOCKET N0. 50/395 OPERATING LICENSE NO. NPF-12 10CFR50.59(b)(2)ANNUALREPORT South Carolina Electric & Gas Co. is submitting the ninth 10CFR50.59 Annual Report for Virgil C. Summer Nuclear Station.
This report contains a brief description of the' changes and modifications made to the facility, as described in the Final Safety Analysis Report-(FSAR)-
and the Fire Protection Evaluation Report (FPER), as well as a summary of the safety evaluations performed to evaluate these changes. Non-conformance notices (identified by their non-conformance notice number [HCN]), procedure-changes (identified by.their procedure number), and modifications (identified by the modification request form [MRF) numbers) were completed during the time frame of one-year prior to August-6 1991, which ended the ninth year-5 following the issuance of the VCSNS Operating License.-
Should you have any question concerning this issue, please call Mr. Manuel W.-
Gutierrezat(803)345-4392 at your convenience.
Very truly yours,-
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R. R. Mahan R. J. White S. D. Ebneter G. F. Wunder-4 General Mancgers NRC Resident Inspector-J. B. Knotts Jr.
RTS (ANN 800)
_ File (818.02-8)-
100097
. NUCLEAR EXCELLENCE - A SUMMER TRADITION!
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- Enclosure to Document' Control Desk' Letter
' ANN 800.'
Page 1 of 15
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I NINTH ANNUAL 10CFR50.59 REPORT VIRGIL C. SUMMER NUCLEAR STATION -
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Enclosure to Document Control Desk Letter ANN 800 Page 2 of 15 NINTH ANNUAL-10CFR50.59 REPORT VIRGIL C. SUMMER NUCLEAR STATION Modificttwon FSAR Revi Notice No.
MRF 21726 This change revised the vertical acceleration and displacement RN 880 for the Service Water Pumphouse, elevation 425 feet, on Table-3.7-7a of the FSAR. Seismic analysis of the_Pumphouse indicated that the vertical acceleration and displacement are lower than the values shown on Table 3.7-7a. =The corrected values are lower than the values used in the original design; therefore, additional stress margin is available for components ' located at this elevation. This change does not involve an unreviewed safety question.
MRF 21562
_ This change revises section 3.8.1 and Appendix 3A of the FSAR-l RN 882 to allow restressing of the Containment Building vertical tendons. Additionally, this change introduces-minor-modifications to the surveillance and retensioning procedure, SP-228m Restressing involves increasing the actual force in the tendon to a point such that further relaxation losses over plant life will not lower the force below the' minimum required by design. Based on the tendon surveillance data, some tendons were found approaching-the minimum technical specification value.- Restressing of these-tendons restored sufficient-load margin over-the minimum required for the remainder of the plant life. -This change does not' involve an unreviewed safety question.
MRF 33284 This change restored the vent connections in the Refueling RN 889 Water Storage Tank'(RWST) to their original designi configuration.. Additionally, the vent piping-from the-RWST to.
the Auxiliary Building-Charcoal Exhaust duct was' upgraded-from l
Non-Nuclear Safety (NNS) to Quelity Related-(QR), as shown on FSAR figure 9.1-3 (drawing D-302-651). Repairing the connections and upgrading the vent piping provides assurance.
that the vent piping will-be functional _following design wind and earthquake loads. This change does not involve an unreviewed shfety question.
MRF 32995 This change installed various barriers to preclude steam RN 893 propagation through floor / equipment drains, from postulated
- high energy line breaks, into rooms-AB 63-01 and IB 51-01 and 51-02, to maintain their mild environment classification. The changes are shosn~in FSAR figure'9.3-10.(drawing E-911-106).
-The installed barriers.will maintain the' environmental:
conditions as originally required-by design. _This change does not involve an unreviewed safety. question.
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Enclosure to Document Control Desk Letter ANN 800 Page 3 of_15 Modification FSAR Rev.
Notice No.
MRF 10393 This change replaced existing _ hose reel isolation gate valves RN 935 with ball valves in the Fire Service Water System.- The installed gate valves leaked excessively. The location of the new installed ball valves is shown on FSAR figure 9.5-1 (drawing 0-302-231). The replacement ball valves will provide a better isolation and sealing characteristic.
The function of the system is not affected by the replacement valves. This change does not involve an unreviewed safety question.
MRF 21613 This change documents the as-installed Alternate Fire RN 935 Service Water System and the Construction Potable Water System. The changes are depicted in FSAR figures 9.2-8 and 9.5-1 (drawings E-302-162,>and 0-302-231, respectively). The alternate fire pumps and components are classified NHS and are not located in areas containing safety related equipment. 'The Alternate Fire _ Service System is not designed to serve any safety related system in the event of a fire. This change does nct involve an unreviewed safety question.
MRF 21351 This change provided Fire Service System connections ~and RN 935 valves to the existing underground supply loop, added a new fire hydr ~t, and relocated some existing ones. The changes are depit in FSAR figure 9.5-1 (drawing 0-302-231).
The connect 1;. and valves were provided to supply = sprinkler-systems in new buildings located outside_the protected area.
Fire hydrants were added or relocated to support new building construction. The connections made to the existing yard piping did not have any significant-effect to the pressure and flow demands of the system. This change does not involve an unreviewed safety question.
MRF 10038 This change upgraded the Liquid Waste and Boron Recycle-RN 937 Evaporator to improve its reliability and capability closer to its design point. ' Changes of piping, valves, instrument and controls, and operating procedures were made in accordance with the guidance in Regulatory Guide 1.143. New piping, instrumentation, and valves are compatible with the design parame!3rs.of existing components.
In addition', the--
-evaporator cooling water supply and return lines are connected to the Component Cooling: Water System Auxiliary Building non-essential headers which isolate from essential plant loads on
- a safety signal. The changes to the FSAR are located in c
Tables 3.2-1, 9.2-3, 9.2-4, 9.2-5, 9.2-6, 9.2-7, 9.2-8, 9.2-9, and 9.2-10; also FSAR figures 9.2-6 and 9.3 18 (drawings D-302-613, and E-302-751, respectively). This change does not involve an unreviewed safety question.
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Enclosure to Document Control Desk Letter ANN 800 Page 4 of 15 Modification 4
FSAR Rev.
Notice No, MRF 21718 This change to FSAR figure 10.4-11 (drawing 0-302-082)
RN 938 replaced the Feedwater Pumps' seal water temperature controllers with new, microprocessor based controllers, I/P converters, and valve positioners. Also, seal water t2mperature switches were deleted. This change provided rel*able, accurate, and efficient instruments on a non-safety related system. This change does not involve an unreviewed safety question.
MRF 21398 This change added a QR designation to piping included in RN 943 Note 1 of FSAR figures 10.3-1, 10.3-2, 10.3-4, 10.4-12, 9.5-11, and 5.1-1,S1 (drawings 0-302-011, D-302-012, 0-302-031, 0-302- 083, D-302-353, and E-302-601, respectively).
This change is needed to indicate the "as-built" system piping and components meeting the quality related requirements. This change does not af fect the design or operatior, of the plant.
This change does not involve an unreviewed safety-question.
MRF 21566 Th..
ange installed drains and drain valves on the skids RN 947 of Instrument Air Compressors XAC-3A and XAC-38._ The_ changes are depicted on FSAR figure 9.3-2 (drawing 0-302-23). The installation of the drains and drain valves do not affect the safe operat'on of the compressors or the plant. This change does not involve an unreviewed-safety question.
MRF 20988 This change replaced the existing Condensate Polisher Sodium RN 953 Analyzer with a new unit. The change is depicted in'FSAR figure 10.4-7a (drawing-D-302-165). The change was'needed due to malfunction and obsolecense of.the existing unit. Sodium is monitored in the polisher effluent to ensure its.
concentration is within prescribed limits specified by procedure. The sodium analyzer does not perform any safety function, nor does it alter the' safe operation of the plant.
This change does not involve an unreviewed safety question.
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Enclosure to Document Control Desk Letter ANN 800 Page 5 of 15 F_SjR Rev.
S Nc'. ice No.
FSAR Rev.
This change to FSAR Appendix 3A revises the VCSNS position Notice 805 on RG 1.137 (regarding the tuting criteria for the. Standby-Diesel Generator fuel 011) to comply with the changes introduced by Amendment 93 to the VCSNS Operating License, issued 11/30/90. This change does not involve an unreviewed safety question.
FSAR Rev.
This change to FSAR figure 9.4-16 (drawing 0-912-138) redrew Notice 883 the drawing for the purpose of enhancing its legibility. No change or revision was introduced to the drawing. This change does not involve an unreviewed safety question.
FSAR Rev.
This change to FSAR figure 8G-4 (drawing E-224-532, sheet 4)
Notice 886 reflects the as-built condition'of the plant. Breaker _for APN5005 position 18 is not Square D but Gould ITE type EElB015. The calculation for-the circuit indicates that the installed b,aker provides adequate protection ~for-the penetration conductor XRP34. This change does not involve an unreviewed safety question.
FSAR Rev.
This change to FSAR Appendix 3A endorses revision 2<of RG 1.32 Notice 891 instead of revision 1 as originally committed. Revision 2 of the guide-deletes the transient load requirements for the Battery Charger without affecting the rest of the regulatory posMions. The Battery Charger'ir sized to handle a transient DC load which will not exceed its nominal' current limit setpoint of 345 amps, for any credible analyzed single failure scenario. This change does not involve an unreviewed safety question.
FSAR Rev.
This change to FSAR section 8.3.2.1.5.2 deletes a-sentence Notice 892 describing the purpose of the battery undervoltage alarm. The deleted sentence incorrectly stated that "a fully charged battery generates a normal float voltage," when actually the float voltage is controlled by the charger setpoint,_
regardless of the battery charge. This change does not involve an unreviewed safety question.
FSAR Rev.
The changes to FSAR figures 9.4-2 and 9.4-4 (drawings Notice 904 0-912-136 and 0-912-147, respectively) reflect the upgrade of the HVAC ducting in the Computer Room Cooling System and in the Control Building Controlled Access Exhaust' ducting _from-NNS to QR. The revision of-the above figures was needed to indicate that the installed ducting is seismically supported
.to preclude failures during a' safe shutdown earthquake. This change does not involve an unreviewed safety question.
Enclosure to Document Control Desk Letter ANN 800 Page 6 of 15 FSAR Rev.
Notice No.-
FSAR Rev.-
This change to FSAR figure 9.3-3a (drawing 0-302-274), adds Notice 905 note " locked open" to valve XVD-2691-IA. to ensure that the design configuration is maintained whenever instrument air is used for breathing air, and it is monitored to ensure personnel sefety. This change does not involve an unreviewed-safety question.
FSAR Rev.
This change to FSAR sections 7.3.2.2.5.9 and 7.1.2.5 adds Notice 906 the Engineered Safety Feature Load Sequencing (ESFLS) input buffer and output relays to the list of components which can not be tested while the reactor is at full power.
In addition, a clarification of the testing provisions is added in agreement with the guidance of RG 1.22. The ESFLS is tested on line, except for the input buffer and output relays which otherwise will require extensive syst0m and breaker alignment; testing-of the relays is performed every 18 months.
Extending the testing frequency of_the relays to 18 months does not degrade the reliability-of the relays to operate on demand. The system design is not changed, and the margin of safety is not affected by the test frequency change. This change does not _ involve an unreviewed safety question.
FSAR Rev.
This change to FSAR figures 9.4-23 and 9.4-24 (drawings Notice 907 0-302-842 and D-302-843, respectively) ensures the properf alignment of the "normally open" Chilled Water valves XVT-6449A-VU, XVT-6380A-VU, and XVT-6360B-VU is maintained by making them " locked open" to guarantee adequate chilled water flow to the Component Cooling Water pump motor (s). This administrative control does not change the system configuration or its operation,__ This change does not involve an unreviewed safety question.
FSAR Rev.
This change to FSAR section 9.5.6.1 provides clarification Notice 908 regarding th6 capacity of-the Emergency Diesel Generator _ Air Starting System Storage Tanks. -The air storage tanks ar' capable of supplying enough air for five successive stars.
without recharging; factory tests demonstrated that they are
-capable of~providing air for 10 consecutive starts, without recharging-and'using both tanks. This change does not alter the original design, the storage capacity of the system, or-its operation, This change does.not involve an unreviewed safety-question.
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Enclosure to Document ControliDesk Letter' ANN _400 Page 7 of: 15 FSAR Rev.
Notice No.
FSAR Rev.
This chance to FSAR figu;es 9.2-8 and 9.2-9 (drawings Motice 909 D-302-161 and 0-302-163, respectively) redrew the drawings to.
enhance _ legibility and added three new FSAR-figures to include ~
all; operating equipment, piping, and' valves in the Water.
y Treatment, Filtered Water Demineralized Water, and Domestic H
Water: systems.. The three new figures are 9.2-10,,9.2-11,--and 1
9.2-12 (drawings E-302-162. E-302-164, and E-302-167, respectively). These drrsings incorporate 1"as-built"-.
j information from the ver tor. These systems do not perform any safety function. This :1ange does not involve an unreviewed -
safety question.-
FSAR Rev.
This change to-FSAR figure 9.3-2'(drawing 0-302-271)Ladds a' Notice 910
" locked _open" note to "normally open" valve XV8-2633-IA.
Instrument; Air Back up Supply Header Isolation Valve', toi ensure that back up instrument air can be supplied on loss _of system pressure. This administrative control does not change the system configuration or its operation. Thi3 change.does-not _ involve an unreviewed safety question FSAR Rev.
This change to FSAR table;6.2-54 and figure 6.2-52 deletes-Notice 911 valve XVG-8105-CS as a containment isolation valve. TP subject valve is in series with valve XVG-8107-CS which is closer to the containment as required by 10CFR50, Appendix A.
Criterion 55.- The-containment isolation valve Technical.
Specification identifies XVG-8107 as the required containment isolation valve. 'This change'does not involve'an Unreviewed safety question.
FSAR Rev.
This change revises-FSAR figures 1.2-28, 10.4-8,:10.4-7A,--
Notice 912 10.4-5, 10.4-6, 9.3-14, 9.3-15, 9.4-25, 9.4-32, 9.5-1, and 9.2-24 (drawings D-302-001, 0-302-101 -D-302-165,- 0-302-201 -
0-302-202, 0-302-352, D-302-'361,(D-302-851, D.302-852, 0-302-231. and D-302-791, respectively) to reflectiWater. Treatment.
Plant equipment details not originally' incorporated in these drawings. The design: basis of the-Water Treatment System _is not affected by J1e addition of.the "as-built"'information.
This change does not: involve an unreviewed-safety question.-
FSAR Rev.
This change to FSAR_ figure 9.3-21 (drawing 0-302-824) adds'a1 Notice 913
" locked open" note to "normally open". valves-IFS-1900A-TVI-LD and-IFS-1900B-TVI-LD.- The-valves provide isolation to the Reactor Building Cooling UnitLleak Detection Flow Switches.
This-administrative control:does not change the system configuration or its operation.:
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Enclosure to Document Control Desk Letter ANN 800 Page 8 of 15 FSAR Rev.
Notice No.
FSAR Rev.
This change to FSAR section 5.2.1.4 indicates that ASME Notice 914 Section 111, Division 1. Code Case N-411, can be used to generate damping floor response spectra curves for the dynamic analysis of piping systems supported from the Reactor Building. The use of new generated floor response spectra and damping curves will result in lower stress values, thus assisting iii reducing in the number of snubbers, moderate energy crack locations, and high energy line break locations.
The reduction of stresses in the piping systems will increase the margin of safety for the reanalyzed systems. This change does not involve an unreviewed safety question.
FSAR Rev.
This change to FSAR figure 11.3-4. sheets 2 and 3 (drawings Notice 916 E-302-743 and E-302-742, respectively) revises the position of valves XVD-7932A-WG and XVD-739B-WG, Recombiner A/8 RMW Inlet Isolation Valves, from "normally closed" to " locked closed."
The administrative control introduced in the operation of 3
these valves affirm their safe and reasonable operation and er.sures that the correct position is maintained. This change does not involve an unreviewed safety question.
FSAR Rev.
This change to FSAR section 9.2.2.5.4 deletes the local Notice 918 indication of component cooling water flow to essential components. The flow transmitters were not procured with indicators. This was reflected on the system flow diagram (circa 1978), but the FSAR text was not changed at the time.
This change does not involve an unreviewed safety question.
FSAR Rev.
This change to FSAR figure 5.1-1, sheet 2 (drawing E-302-602)
Notice 919 revises the position of valves XVN-8050-RC and XVC-8051-RC from " throttled" to " locked as is," and valves XVT-8021-RC from " closed" to " locked closed." This change is made to ensure that valves XVN-8050-RC and XVN-8051-RC allow reactor coolant flow to maintain the pressurizer sprty nczzle at about the same temperature of the spray flow, thus preventing thermal shock of the nozzle: valve XVT-8021-RC is locked closed to ensure that the pivssurizer power operated relief valve seal is maintain.>d. The changes introduced in the operation cf the valve affirm the safe aiid reasonable operation of components and systems and ensure that the correct de;-Jn position is maintained.. This change does not involve-an unreviewed safety questlom FSAR Rev.
This change to F.AR figure 5.1-1, sheet 1 (drawing E-302-602)
Notice 920 revises the posi..lon of valv3 XVM-8076-RC, Reactor Vessel Leakoff Telltale Dr&ie. W.1ve, from "normally closed" to.
'" locked closed." 'ihe administrative control introduced in the operation of this valve affirms its' safe.and reesonable operation and ensures that the. correct design position is maintained. This change does not involve.an unreviewed safety cuestion.
Enclosure to Document Control Desk Letter ANN 800 Page 9 of 15 FSAR Reva Notice No, FSAR REV.
This change to FSAR figure 9.3-16 (drawing E-302-677) corrects Notice 921 the tag number of the Boric Acid Pump No. 2 inlet isolation valve to the correct number 1-83128-3-X420. This is an administrative change not affecting the design or operation of the plant. This change does not involve an unreviewed safety question.
FSAR Rev.
This change to FSAR section 13.1.2 updates the operating Notice 922 organization structure and qualifications of its memoers. The changes introduced in the operating organization do not affect the design, testing, or operation of the plant. This change does not involve an unreviewed safety question.
FSAR Rev.
This change to FSAR section 13.5.2.4 modifies the 1
Notice 925 identification of the Annunciator Response Procedures (ARP) to conform with currently used numbering system for ARPs and to be consistent with the alarm panel numbering on the control board. The existing numbering system was described in VCSNS's response to NUREG-0700, guideline 6.3.4.36.
It has been in use since initial operation, and the operations personnel hre very familiar with it.
This change does not involve an unreviewed safety question.
FSAR Rev.
This change to FSAR figure 6.2-46 (drawing 0-302-661) corrects Notice 926 the position of certain valves and depicts some missing piping compenents to conform with the "as-built" configuraticn and the verified system alignment for operation. This change is administrative in nature and does not represent a design change. This change does not involve an unreviewed safety question.
FSAR Rev.
ThischangetoFSARfigure9.1-3(drawing 0-302-651) assigns Notice 927 a tag number to the Fuel Transfer Tube Valve. The valve did not have a component identification number. This change is administrative and does not alter the system configuration or its operation. This change does not involve an unreviewed safety question.
FSAR Rev.
This change to FSAR figure 9.4-22 (drawing 0-302-841) revises Notice 928 the output of the level transmitters on the Chilled Water Yystem Expansion Tanks to show that the level transmitters output is not inpat to the TSC computer. The transmitter provided signal for level h.Jication and alarm in the control room and did not input to the TSC. This change does not involve an unreviewed safety question.
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Enclosure to Document Control Desk Letter ANN 800 Page 10 of 15 FSAR Rev.
Notice No.
FSAR Rev.
This change to FSAR sections 9.3.1.3, 9.4.1.2.1, and Notice 929 10.4.7.2.3 reflects the installation of safety related air accumulators for the feedwater Isolation Valves and the Control Room Outside Air Dampers. The air accumulators for these components were not identifiad on the subject sections.
The Control Room Outside Air Dampers require air to open to maintain a positive pressure within the control room boundary.
The feedwater Isolation Valves require air to operate, and their closure is an essential function for isolation of the feedwater flow. The air sccumulators maintain the functional capability of the components upon loss of Instrument Air System pressure. This cht.nge does not involve an unreviewed safety question.
FSAR Rev.
This change to FSAR tables 9.1-1, 9.3-5, 9.3-6, and 11.2-2 Notice 930 replaces various filter cartridges with smaller micron rating cartridges. -The replacement cartridges provide additional removal capacity of CoS8 and Co60, two of-the major contributors of coolant activity. The new cartridges are designed to pass the same amount of flow and collect smaller size particles. The reduction of particle size for the new cartridges will contribute to the reduction of dose rates.
This change does not involve an unreviewed safety question.
FSAR Rev.
This change to the FSAR, Appendix 3A, documents an exception Notice 931 to the length of time-involve in an annual and triennial period to allow some degree of tolerance, particularly in the positive direction. The annual period will cover one year plus or minus one month; the triennial period will cover three-years plus or minus three months, both from the date of previousaudit,orannualinspection(forannualperiod).
It is improbable that a vendor QA program, which has been acceptable for the preceding years, will change adversely during a one/three month extension. This change does not involve an unreviewed safety question.
FSAR Rev.
This change to FSAR figure 9.3-16 (drawing'E-302-677) corrects Notice 932 the tag number of valve XVD-8307-RC. Boric Acid Batch Tank Drain Valve. This change is administrative in nature and does not alter the system configuration or its operation. This change does not involve an unreviewed. safety question.
FSAR Rev.
This change to the FSAR, Appendix 3A,' sections 17.2.15.2 and-Notice 933 17.2.16.2, deletes the biennial review of plant procedures and makes an administrative change of responsibilities from the Procurement Quality group to the Station Quality Systems group. Deletion of biennial reviews was approved by the NRC in their letter of November 29, 1990.- This change does not involve an unreviewed safety question.
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Enclosure to Document Control Desk Letter ANN 800 Page 11 of 15 FSAR Rev.
Notice No.
FSAR Rev.
This change revises FSAR figures 8.3-1, 8.3-2, 8.3-2aa and Notice 934 adds new 8.3-2ab (drawings E-206-062, sheets 1, 2, 3, and 4).
These one-line diagrams have been redrawn on CADO. No technical changes were incorporated. The drawings were
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reformatted for enhanced clarity and legibility.
This is an administrative change which does not change the drawings.
This change does not involve an unreviewed safety question.
FSAR Rev.
This change to.FSAR figures 10.4-8, 9.4-32, 9.4-25, 9.3-15, Notice 935 9.3-14, 9.5-1, 10.4-6, 10.4-5, 10.4-7A, 9.2-24 and 1.2-28 (drawings 0-302-101, 0-302-852, 0-302-851, 0-302-361 0-302-352, 0-302-231, 0-302-202, 0-302-201, 0-302-165, 0-302-791, and 0-302-201, respectively) was made to reflect piping-continuation and grid locations. The changes are administrative in nature and do not change the systems configuration or their operation. These changes do not involve an unreviewed safety question.
FSAR Rev.
This change to FSAR section 17.2.1.4 deletes the title of Notice 940 General Manager, Administrative and Support Services, since this position is no longer part of the VCSNS organization.
This administrative change does not involve an unreviewed safety question.
FSAR Rev.
ThischangetoFSARfigure9.5-1(drawing 0-302-231) changes Notice 944 the position of Alternate Fire System Pump Header manual isolation valves XVG-6007-FS and XVG-6010-FS from "normally open" to "normally closed." These valves are closed'during normal system operation. They are intended for isolation of the test header when.the pumps are tested.-Changing the position of the valves to "normally closed" does not alter the-function of the system. This change does not involve an unreviewed safety chestion.
FSAR Rev.
This change to the following FSAR sections: 13.1 updates Notice 945 the responsibility of the Technical Services Manager and personnel under him; 13.6 incorporates changes omitted in previous organizational changes; 9.2.7.2,.9.2.4.1.2 and FSAR figure 3.18-17 reflect administrative corrections. -The changes-introduced do not affect the design, testing, or operation of the plant. This change does not involve an unreviewed safety question.
FSAR Rev.
This change to table 3.2-1-incorporates the relief provided Notice 948 to licensees by Generic Letter 89-09 regarding procurement of replacements not currently available.in full compliance of Section III of the ASME code. This change does not involve an unreviewed safety question.
y Enclosure to Document Control Desk letter ANN 800 Page 12 of 15 FSAR Rev.
Notice Not FSAR Rev.
This change to FSAR figure 5.5-4 (drawing E-302-641) revises r-Notice 949 the position of valves XVT-0003A, XVT-0003B, XVT-0016A and gl XVT-0016B, RHR Header A/B Drain Valve and RHR Header A/B Vent f
Valve, from "normally closed" to " locked closed." The f.
administrative ccntrol introduced in the operation of these y
valves affirm their safe and reasonable operation and ensures correct design position. This change does not involve an unreviewed safety question.
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Enclosure to Document Control Desk Letter l
1 ANN 800 Page 13 of 15 Nonconfortnance
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-4096 Valve XVC-6410A-VU, Nonessential Equiprent Outlet Chilled Water Return Header A Check Valve, failed an operdbility test performed to demonstrate the valve is able to close. The valve failed the test when low differential pressure was
. measured across it. The function of this valve is to close to prevent chilled water backflow from safety related loads to non-safety related components. This valve is in series with check valve XVC-06489A-VV. This valve is also listed as an active valve. The valve disc was tack welded in the closed position to eliminate its active function.
With the valve secured in its safe position, the potential of valve failure is eliminated. This NCN and its disposition does not involve an unreviewed safety question.
l FPER Rev.
Notice No.
FPER-895 This change to FPER sections 4.4.2.!
2.2, 4.4.6.1, and 4.4.6.2 includes the addition of_new u.,ineered Safety Feature replacement batteries in the fire loading for the fire areas in these section:. Evaluation of the effect of the increased combustible loading from the larger battery cases indicates that the conclusions drawn in the FPER for each individually affected area remain valid. This change does not involve an unreviewed safety question.
FPER-923 This revision to FPER drawing E-023-001 documents the installed condition of the Alternate fire Service and Construction Potable Water System. Neither system is related to any safety function. Both are located in areas not enclosing safety systems, and neither interacts with any safety related or quality related system or component. This change does not involve an unreviewed safety question.
FPER-939 This_ revision to FPER sections 3.1.5, 3.2.2.4, and'3.2.3 changes the numbering of Fire Emergency Procedures to-satisfy human factors considerations. The new numbering will be consistent'with Emergency Operation Procedures. This change is administrative _in nature. This change does not involve an unceviewed safety question.
FPER-941 This revision to FPER drawing _ E-023-021_ changes the designation of presently' identified room 36-13 to 36-17E.
This change is administrative in nature. This change does not involve an unreviewed safety question.
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Enclosure to Document Control Desk Letter
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ANN 800 Page 14 of 15 Procedure Revision EPP-001 Activation and Implementat on of Emergency Plan.
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revision assigns responsibility for changing emergency classifications. This revision is intended to clearly show who is responsible for changing emergency classifications and does not affect the conduct of operations during an emergency.
The revision to this procedure does not involve an unreviewed safety question EPP-024
[onduct of Drills and Exercises.
This revision adds a section for remedial exercises, revised attachment I to specify scheduling of communications drills, and added a list of pre-drill communications checks. The changes introduced are administrative in nature and are intended to improve the emergency response readiness of plant personnel. The revision to this procedure does not involve an unreviewed safety question.
PTP-250-001 0xvaen Leak Testina.
This procedure is intended to test the main condenser oxygen removal capability.
The tests described by this procedure do not affect the design or operation of the plant.
Implementation of this test procedure does not involve an unreviewed safety question.
SAP-101 Statement of Responsibilities General Manaaer. Nuclear P iant Operations. lhis revision assigns additional responsibilities to the General Manager, Nuclear Plant Operations. These additional responsibilities were assigned previously to the General Manager, Operation and Maintenance, a position that does not exist due to reorganization, lhe changes introduced are administrative in nature. The revision to this procedure does not involve an unreviewed safety question.
1 SAP-133 Desian Controjf_Lmplementation and Interfa.e. This revision deletes portions of this procedure redundant to procedures ES-416. D.esian Modification Chance Process and Control, and ES-419, Limited Scope Desian Chances.__ Request for Enaineerina Evaluation and Ecual To/Better Than Evaluations, This revision is administrative in nature. The revision to this procedure does not involve an unrevicwed safety question.
SAP-1120 Operatina Experience. This new procedure implements Management Directive No. 17 to establish administrative guidance for processing operating experience issues, including industry-wide and in-house. This procedure does not involve facility changes, operational activities, tests or experiments. This procedure only involves the processing of operating experience issues. This procedure issuance does not involve an unreviewed safety question.
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Enclosure to Document Control Desk Letter ANN 800 Page 15 of 15 Procedure Revision SOP-212 Operation of the Nuclear Blowdown System, This revision allows for processing the effluent from the Nuclear Blowdown Holdup i
Tank via a system drain line to the Turbine Building sump.
The pathway for: processing the Nuclear Blowdown Holdup Tank effluent is part of the system original design, as shown in FSAR figure 10.4-14.. The pathway is from a normal system drain to the sump and from the sump drain to the Turbine Building Sump. The revision of this procedure does not I
involve an unreviewed safety question.
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