ML20059A618

Forwards List of Changes to 10CFR50.59 Rept for 1984 Covering Changes,Tests & Experiments

ML20059A618
Person / Time
Site:	Robinson
Issue date:	07/23/1985
From:	Morgan R CAROLINA POWER & LIGHT CO.
To:	Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
RNPD-85-1802, NUDOCS 9008230135
Download: ML20059A618 (14)

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Unrolina Power & Light Company i a-ROBINSON-NUCLEAR-PROJECT-DEPARTMENT POST 0FFICE BOX 790 .

HARTSVILLE, SOUTH CAROLINA ~ 29550 JUL 20 M

~ Robinson File-Nos' 13510: -Serial: RNPD/85-1802

Dr. J.. N. Orace Regional;: Administrator "'

-United.-States Nuolear Regulatory Commission Region II- .

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101 Marietta' Street, N. W., Suite 3100

-Atlanta', Georgia 30323

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N H.B. ROBINSON STEAM ELECT c LANT UNIT-NO. 2  ?'-

. DOCKET NO. 50-2 1 2 ]d LICENSE NO. 3 w .l 1984 CHANGES TO THE FACILITY REPORT a..

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DearcDr. Graces

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' Carolina-Power land-Light Company /CP&L) furnishes the-enolosed- ' '

', list of:-changes) to the, f acility- .escribed in the FSAR-pursuant--

.to 10CFR50.59.- '

In. addition, it is reported, pursuant to NUREG 0660, Item II, C.3 3, that the Pressurizer Safeties a' d Power Operated Relief Valves were

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Jnot.Lohallenged during 1984. 1

-Iriyou have any questions concerning this report, please contact me.

q' Very truly yours, j m

R bl E. Morgan

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General Manager '

H. B. Robinson S. E. Plant i

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. Enclosure 9000230135 850723 .

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PDR ADOCK 05000261 c0: H. E. P. Krug R- PDC )

J. M. Taylor

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Enclosure to Serial .RNPb/BS-1802 y: ,

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'y; t ATTat=enems? 1 f a 1984.

5. B. ROSTRSON UNIT 2 I

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f CRANGES, TESTS AND EXPERIMENTS PURSUANT TO 10CFR50.59 1.0 As permitted by 10CPR50. 59 (a) (1) , ePanges were made at NBR that changed the facility as described in the Updated Final Safety Analysis Report but did net constitute unreviewed safety questions. They did not

. require revisions to the Technical specifications, or revisions to the Technical specifications were not required prior to initiation. The changes did not adversely affect the safety of the plant or' the health and safety of the general public. These changes are as follows:

1.1- Strainers were added in the drain lines f rom the . fuel handling building to stsp tank "B" and in the lines f rom the laundry and hot shower drains to the laundry j.' and hot- shower drain tanks "A" and "B." (Mod. N9.

340).

1.2 Selected actuation and alarm features of the F!re Detection and Actuation System were = modified to enhuce

,_ system operability and to correct confusing and inap-oropriate alarms. (Mod . No . 4 4 5X) .

1 1.3 A reactor coolant gas vent system was installed. This modification provides a system for venting non-condensible gasses from the reactor vessel head'and the przasurizer daring post accident situations to assure i

that core cooling during natural circulation will not be inhibited. (Mod. No. 520).

1.4 A sample line was provided from each of the fear containment air recirculation cooling unit motor cooler discharge lines to the inlet side of the air cooling L - _ _ _ _ _ -_ _ - _ _ _ __ _ --- _ --- ------- - -

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v coil discharge line radiation monitor. This l modification will provide the capability of monitoring l radiation from both the air cooler and motor cooler  !

discharge lines. (Mod. No. 604).  !

1.5 The pressurizer spray valves, spray bypass flow valves  ;

and temperature transducers were replaced and relocated. This modification is required to facilitate

, valve maintenance and upgrade. system performance and. r reliability. (Mod . No. 612) .

1.6 A sealing bladder was added internal to the condensate  ;

storage tank. This modification will prevent oxygen i i

absorption at the surf ace - of the condensate water.

i (Mod. No. 6S0). ;t 1.7 Feedwater heaters 2, and 2 were replaced with new heaters and with stainless steel tubing. This modifi- ,

cation will reduce the source of copper from the I secondary water side thereby enhancing steam generator l reliability. (Mod. No. 681) . .i t

1.8 The main service water discharge line was rerouted f rom ee dische 'e of the component cooling heat exchangers pe ne t r ating se east wall of the reactor auxiliary  ;

Fu;1 ding, to the condenser discharge line just east. of l

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1:he turbine building. This modification relocater, the service water line from under the site of the new i radwaste facility. (Mod. No. 686). ,

1.9 Two existing fire hydrants and PIV's were relocated to the north yard erea to better cover the area, the fire loop in the northwest corner was rerouted around the l i new hot lab, and a leg and PIV for future expansion of

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the fire main were added. These changes improve the fire loop coverage and provide for expansion of the (Mod. No. 716).

fire main.

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a 1.10 The existing' fire -loop was extended westward to provide

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fire protection water to six new buildings and eight l new hydrants. (Mod. No. 716).

l 1.11 cab 1e and necessary hardware was ir. stalled to provide  !

temporary 480V power to RHR Pump A or B from the 480V  !

DC bus spa r '- compartment. In the event the existing f power feeds are damaged by ffre, this mos'.l f ica tion i

provides a method of supplying temporary electrical  !

power for operation of one of the- RHR pumps. (Mod . No . l 710S).

1.12 The three original steam generator tube bundles were '

replaced with new tube bundles incorporating design  !

improvements. The design improvements incorporated a into the new tube bundles include the following items:  ;

a. A nominally flush tube-to-tube shee t configuration f on the tubesheet primary side.

b. Full-depth expansion of the tubes in the-tubesheet holes. I i

c. Additional secondary side handholes just above the i

tubesheet.

d. Inclusion of a three-inch inspection por *, un the tube lane in the top region of the tube bunale.

e. Tubing with thermally treated Inconel 600 material with the innermost eight tube rows stress relieved after tube bendina,

f. Tube support plates incorporating a quatrefoil hole design.

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s. Tube support plates fabricated from stainless-steel material.

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h'. A secondary side flow distribution baf fle located above the tubesheet.

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1. A tube lane flow blockage device on the secondary '

side.

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Capability for increased blowdown flow.

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k. Additional tube marking on the primary coolant l side of-the tubesheet. '

In addition to replacing the tube bundle, the following modifications were made to each steam domes

a. A new feedwater ring, with Inconel J nozzles, and new ring supports were insta11eo.

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b. A new f eed*;4 te r nozzle end piece and thermal sleeva (welded to the feedring) were installed.

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c. A steam nozzle flow limiting device was installed (

l and the old perforated plate essentially removed.  ;

While there are some diffr aces between the original and the new steam generators, the- performance -para- I meters are the sarae, thus plant operations is unchanged i from the original as a result ~ of this project. .This.

modification removes the limitations imposed by the Reduced Temperature Operations described in Appendix 1.1A of the HBR2 UFSAR. (Mod . No. CAP 713) .

1.13 The mesh-pad demisters in the moisture sepsrator reheaters were replaced with stainless steel chevron l

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demisters.

L. This modification a , eliminates the drain i 6: plugging problems caused by the mesh-rad demister '

tailings. (Mod . No. 719) . I 1.14 The 3-way isolation valves upstream and down-stream of heater train 3, 4, 5 A and B were replaced with double '

isolation valves. This modification will allow iso- ,

lation of each feedwater train (3, 4, 5 A and B) for maintenarce while still allowing' flow to the AFW header. (Mod . No . 720) 1.15 A feedwattr recirculation line (piping, valves, etc.)

was; installed from the feedwater discharge side of the HP feedwater heaters 6A .ind 6B to the inlet side of the condensate polishing system via the main condensate l pump B suction piping. This modification allows '

I removal of ' corrosion product buildup from the condon-  ;

sate and feedwater systems. (Mod . No. 7 2 2) . )

l 1.16 A condensate polishing O' stem located downstream of the condensate pumps and upRtream of the gland steam  !

condenser was installed.to maintain the steam generator water chemistry within specifications. l (Mod. No. 723- i and Work Package W-019).  !

l 1.17 The piping supports for the seven pressurizer safety and relief valves were structurally modified so that they are adequate to support loads resulting from the Westinghouse piping system stress analysis. This modification assures that all supports on this piping conform to the original criteria. (Mod . No . 729).

1.18 Thermal insulation and a electrical heating system were installed for the RWST capable of maintaining the water temperature at 900F. This modification was installed I to reduce the potential for thermal shock to the I

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i reactor vessel, however, it is not required and will-not normally be operable. (Mod . No . 7 3 7 ) .

i 1.19 The . makeup water treatment system was upgraded by replacing the vacuum degasifier with a larger unit l

' including new vacuum pumps, transfer pumps, and asso- l ciated interconnecting piping and valves. This I modification will provide the plant with a design makeup water capacity of 300 gallons per minute and- I improve overall water quality. (Mod. No. 738).

1 1.20 Post indicator valve FP-10 was removed and an under-ground valve box installed in its place. This modifi- f cation was required to provide roadway traffic l clearance. (Mod . No. 7 4 5) . I J

1.21 A steam generator wet layup system, connected to tM existing steam generator blowdown piping, was installed. The internal water mass in each steam ,

generator can now be tecirculated in either the upward l or downward flow direction utilizing the respective drain / wet layup pump for circulation through portions l

of feedwater or blowdown piping.- (Mod. No. 747). -

1 L 1.22 A lab / waste sump tank and pump were installed to i service the E&RC building. Discharge from the sump i L pump is sent to the auxiliary building radwaste sump-tank B. (Mod . No . 7 4 8) .

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1.23 Piping, HVAC and electrical / instrumentation / control-systems necessary to support the capability to connect an external hydrogen recombiner were installed. The hydrogen recombiner and control panel are shared with another utility and transported to the site when required. This modification meets the requirements of  :

10CFR50.44. (Mod. No. 750).

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G ( % ga 7 of 13 1.24 The high voltage alarm bells in the south cable vault room and the cable spread room were removed. These high voltage alarm bells indicate " System Fire" and do not .mean fire in the rooms. This modification will delete the alarms which have caused plant personnel to evacuate the areas unnecessarily. Evacuation alarm-bells are provided for these areas. in case of fire.

(Mod . No. 751).

1.25 To additional electrical containment penetration assemblies were installed. These penetrations are the capsule type design which have double pressure barrier protection ~ in the header plate and, therefore, require an endplate at one end only. This modification was necessary to meet Appendix R requirements. (Mod. No . . !

755A). ,

I 1.26 Emergency lighting for access, operation, and egress for the control panels and equipment res red for safe shutdown was added. This modification was necessary to meet Appendix R' requirements. (Mod . No. 755D) .

1.27 The existing fire detection system installed in Fire Zone 12 was extended and one fire detector added., This modification provides fire detection coverage for the hallway area at the junction of Zones 12 and 13 to meet Appendix R requirements. (Mod.'No. 755E).

1.28 The existing dedicated shutdown cables routed in Fire Zone 24 were replaced with cable having a non-combustible radiant energy shield where the 20 foot 1

separation criterion or a suppression system does not exist, or where the conduit is not wrapped with fire rotardant material. This modification was necessary to meet Appendix R requirements. (Mod . No. 7 55I) .

ss 8 of 13 T 1.29 0- Piping and v41ves were installed to provide sources of j d treated water to the E&RC building, from the primary I water system and the demineralized water system. (Mod. -

No. 757).

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1.30 Stainlecs steel caps were installed on the atmospheric l vents on waste condensate tanks C, D and E. This '

modification will prevent the release of potentially t contaminated water onto the ground outside the auxil-  ;

iary building. )

The tanks are still protected from 1 collapse by overflow lines. (Mod . No. 7 58) . I -

1.31 The paddle type flow switches on the containment HVH  !

L units were replaced with more reliable differential -

pressure units. A subsequent modification changed the  !

high pressure tap' for the D/P switch from the atmos- I phere to the discharge side of the fan. These modificationa will improve the operation and relia-bility of the flow switches. (Mod. Nos. 760 and 846) .

L 1.32 Pulsation dampeners were installed on the ' discharge  ;

lines and suction stabilizers on the suction lines 'of  !

the charging pumps. This modification will improve i '

system performance by reducing vibrations in the CVCS piping. (Mod. No. 766). ,

1.33 Automatic flow control was installed on the auxietary feedwater system. Equipment added included electro- '

hydraulic actuators on AFW pump discharge valves, flow measuring loops, and flow indicators / controllers.- This modification will provide automatic flow control '

operation throughout the full range of both normal and l* potential Gmergency modes of operation. (Mod. No.

767).

1 1.34 The copper U-bend end HVH f an and motor cooling coils f were replaced with cooler coils of stainless steel l

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tubes with water boxes on end. This modification will minimize corrosion by use'of stainle" steel tubes and 3 eliminate erosion-induced leakage caused by the U-be nd s '. (Mod.-No. 769).

I 1.35 Supervisory equipment was added to the HBR2 230KV switchyard to provide the CPfiL Skaale Energy Control Center in Raleigh, NC with parallel control, indi-cation, annunciation and metering of the 230KV trans- J mission lines and switchyard at the Robinson plant.

Indication and metering is only provided on the Unit 2 N north bus 230KV and the Unit 2 Darlington tie 230KV , 'I circuit- breakers. This modification has also upgraded the oL feed to the 230KV relays to provide greater reliability. (Mod. No. 771).

1.36 The secondary sampling system was upgraded by instal- .l ling new state-of-the-art hardware and instrumentation I in an enclosed climate controlled room. The system was '

also connected to the existing steam generator manual sample lines to provide continuous samples from the steam generator blowdown lines. (Mod. No. 774).

1.37 The source of the RHR input to the PASS was relocated to provide an increased flow rate for sampling the reactor coolant water. This modification will provide increased flow rate to both the primary sampling system and the PASS. (Mod. No. 777).

1.38, A Digital Metal Impact Monitoring System was installed ,

to provide information for early detection of a loose I part in the RCS. (Mod. No. 783).

1.39 Debris screens were installed on the inboard side of the containment pressure and vacuum relief valves, */12-

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F 's 11 and V12-13. This modification will enhance the L reliability of the containment isolation valves by j; 'prevanting airborne debris f rom ' interfering with tight closure. (Mod . No . 7 8 5) .

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( l.40 The chemical feed system was modified to replace  !

cyclohetflamine with ammonium hydroxide as the pH I additive to be injected at the discharge of the conden- I sate polisher. The hydrazine addition system was also l modified to change the location of the injection points {

in the condensate system. (Mod. No. 787). t

.,1.41 The equipment required for post-fire repair of PORV 1 control / power circuits was installed. This modifi-cation provides new cable terminations and conduit from 1 the existing DC 480V distribution panel to 125V DC ,

, power panel A in the 4160. switchgear room. (Mod. No.

795A).

i 1,42 An automatic shunt trip for the reactor trip breakers '

was installed. The trip is designed to operate in  !

parallel (redundant) with the undervoltage trip function. This modification meets the. requirements of NRC Generic Letter 83-28, " Required Actions Based on Generic Implications of Salem ATWS Events," paragraphs 4.2 and 4.5. (Mod. No. 799).

1.43 The limitations of the low Tave program, which were set a by Modification M-627 in an ef fort to prolong the life of the steam generator tubes, were removed. With the F replacement of the steam generator tubes, this modifi-cation returns t.he Tave program and all associated setpoints to the 2300 MWT values which were used ' prior to November 1981 when the low Tave program was I implemented. (Mod. No. 801).

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j 1.44 Rigid metal reflective stainless steel insulation boxes were installed to encapsulate the pressurizer safety i valve piping between the , pressurizer and the safety  !

valves. This modification, which is in partial response to Item II .D.1 of NUREG 0737, will passively I increacc loop seal temperatures to the acceptable l levels previously expected by Westinghouse. fluid hydraulic analysis for the safety valve discharge ,

piping.- (Mod. No. 606). i 1.45 Several improvements were made to the Post Accident sampling System including corrections of problems identified during turnover and closeout of. the PASS.

These improvements included; 1) protecting V-4180 from primary pressure, 2) providing permanent thermocouple'  !

readout, 3) providing a flow path to the chemical' drain ti 1

tank, 4) protecting radiation monitors from containment-pressure, 5) adding H2 and 02 supply bottles and,

6) adding heat tracing to containment air sample lines.

(Mod. No. 810).

1.46 A partial length control rod drive mechanism was replaced with a welded cap atop the reactor vessel head r at the K-6 core location. This modification will  !

aliminate the reactor coolant leakage which ' occurs at this point. Since the mechanisms for partial length I toda are no longer functional, no operational impact results. (Mod. No. 815).

1.47 A twat boundary valve was installed inside containment on the non-safety-related portion of the nitrogen supply to the pressurizer relief tank. (Mod . No. 821) .

1,48 Three RTD bypass valves (V-554A, V-556A, and V-559A) in RCS loop A were removed and replaced with straight l pipe. These valves experienced stem to disc separation i

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. Op G[ cts 12of13 which cannot be repaired. The offacts on 'the- RTD '

bypass loop flows created by this modification are being evaluated and the hot and cold leg orifices modi-fled . to ensure proper flow and balancing in the loops.

(Mod. No. 827).

- 1.49 Relay logic was added to the safeguards system to -

! initiate a close signal to turbine building service water isolation valves V6-16A, V6-16B and V6-16C on undervoltage of emergency bus El or E2 for one minute coincident with a safety injection signal. This modi- '

fication. will prevent the low pressure degradation of n

the service water system under unusual conditions. The worst case of degradation would be if during an accident condition, one of the emergency busses could not be energized causing only - two service water pumps" to run. Under these conditions, the turbine building service water isolation valves would be given' a close signal. (Mod. No. 828). -

r-1.50 The loads on Train A 125VDC battery were reduced by ,

removing the air side oil backup pump motor and tht-emergency bearing oil pump motor non-safety-related These loads were placed on a new Train C loads.

l battery system consisting of a battery charger, storace battery, power feeders to the battery charger and MCC.

These modifications were necessary to reduce t " loads on MCC A to allow the Train A battery to pass its F

service test as required by RG 1.129. (Mod. Nos. 830 and 831) .

1.51 The CCW surge tank vent valve (RCV-609) was blocked -

open to provide free venting of the tank to the WHUT.

This modification was done in response to a 10CFR21 report issued by Westinghouse stating that continued j use of this valve could present the possibly of CCW j systen) overpressurization. (Mod . No. 835). ]

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>,, . m Pcgs 13 of 23 1.52 The feedwater low presa1re heater relief valves were replaced and the isolatica valves for these relief

. valves ~ were removed during October 1984. Since then, the , isolation valves were found necessary during startup to prevent undesirable lifting of the ' relief valves. The isci.aiion valves were reinstalled to isolate the relief valves during condensate . pump startup. Rollef isolation valves - w!11 be locked open-prior to sending any extraction steam to the feedwater heater shell side. (Mod. Nos 823 and 842).

1.53 The automatic shutdown feature on high radiation signal was removed from RMS-20 for the fuel handling building ventilation fans HVE-14 and HVS-5. This modification also reinstates the overload protection which was not connected to HVE-14. As the FEB is not airtight, the modification was necessary to ensure that any *eleases will be monitored and filtered by the ventilation exhaust system. (Mod . No. 714 ) .

1.54 The bellows expansion joint which connects the RHR supply piping- (P-17) with its penetration sleeve (S-4) was removed and an end cap installed in place of the removed expansion joint. The end cap will serve as.a rigid restraint on this piping system. This modifi-4 L cation is necessary to provide an Improved restraint to '

the RHR supply - piping to satisfy an EBASCO IE Bulletin 79-14 analysis. (Mod. No. 647).

l 1.55 Flow measuring equipment was added in the main steam

[ supply lines to the moisture separator reheaters. This L modification will provide a means of detecting tube ,

leaks in the MSR at an early stage and for detection of heat load changes. This equipment is located down-stream of the main steam containment boundary isolation valves. (Mod. No. 481).

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