ML20215F095
| ML20215F095 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 09/29/1986 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 8610160078 | |
| Download: ML20215F095 (5) | |
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Public Service Electric and Gas Cornpany Corbin A. McNeill, Jr.
Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge. NJ 08038 609339-4800
- Vice President -
Nuclear..
September 29, 1986 U. S. Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406 Attention:
Dr. Thomas E. Murley, Regional Administrator Gentlemen:
INITIAL START-UP TEST PROGRAM CHANGES HOPE CREEK GENERATING STATION DOCKET NO. 50-354 In accordance with license condition 2.c.10 of Operating License NPF-57 and ' the provisions of 10 CFR 50.59, Public Service Electric and Gas Company (PSE&G) is submitting 39 copies of the changes made to the Hope Creek Initial Start-up Test Program.
This program is described in Chapter 14 of the Final Safety Analysis Report (FSAR). contains a description, justification, and safety evaluation for each change.
Attachment 2 contains the marked-up FSAR pages incorporating these changes.
Per the requirements of 10 CFR 50.59, paragraph (a)(2), none of i
these changes involve an unreviewed safety _ question.
The safety evaluations in Attachment 1 provide the basis for this conclusion.
i If you have any questions in regard to this matter, please do not hesitate to contact us.
i Si cerely, Corbin A. McNeill Attachments 1
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860729c P
05000354 5pb PDR G
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r-Dr. Thomas'E. Murley 2
9/29/86 Regional Administrator C.
Mr.
D.
H. Wagner USNRC Licensing Project Manager Mr. R. W.
Borchardt USNRC Resident Inspector Mr. - J. M.. Taylor Director -JInspection and Enforcement 4
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9 I
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ATTACHMENT 1 DESCRIPTION OF CHANGE This change to FSAR Figure 14.2-5 indicates that the Loss of Offsite Power (LOP) Test (Test #30) was not completed in Test Condition #1.
Inntead, it will be completed and reviewed in either Test Condition #2 or Test Condition #3.
The change clarifies that the test will be performed with the generator synchronized to the grid at approximately 20% reactor power.
REASON FOR CHANGE The LOP Test was not completed in Test Condition #1 due to logic card modification checks.
The test was attempted in Test Condition #2 and was aborted due to failed test criteria.
This change is in line with the FSAR test description, Reg Guide 1-68, and vendor specifications.
10 CFR 50.59 SAFETY EVALUATION Pursuant to 10 CFR 50.59, paragraph (a)(2), the following three questions are responded to in order to determine if an unreviewed safety question is involved in this change.
1.
Does the probability of occurrence, or the consequences of an accident or malfunction of equipment, important to safety previously evaluated in the FSAR increase?
No.
Changes do not alter the original plant performance testing.
Test is conducted at the same plant conditions as originally required.
2.
Is the probability for an accident or malfunction of a different type than any previously evaluated in the FSAR created?
No.
Changes do not alter test methodology nor do they place the plant in an unsafe condition.
Test transient is enveloped by the PSAR Chapter 15 analysis.
Cold retests of modified systems are performed prior to performing this test a t powe r.
3.
Is the margin of safety as defined in the basis for any Technical Specification reduced?
No.
None of these changes are related to Technical Specification requirements.
Since the response to these questions is no, the change does not involve any unreviewed safety questions.
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ATTACHMENT 2
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TEST OPEN HEAT tens er 2 (21) Ph during _
TEST NAME 1
2 3
4 5
6 conditens on F ipsre 14.2 4 from tem cond6 ten 8 VESSEL W
. (2) Perform Test 5. timing of 4 (22) The tem nundier sorrelates se 1
Chemecaland Radiochemical X
X X
X X
selected contrai reds. in FSAR Section 1 A2.12.3Ji 2
Radiaten Mesessment X
X X
compancten usth expected h a W h met 3
Fuse Loading
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Fun Core Shutdown Mar 1Pn 8
(3) Dynamic System Test Case to (23) May be performed any time test f' f
5 Contros Rod Dreve X
X Xm XW XW be completed between test condstoons permit 6
SRM Performance J(
condaions 1 and 3 8
iRM Performance X
X (24) RCIC testing If not previously l
l 9
LPRM Catereten X
X X
X rai c imion per onned 10 APRM Calibraten X
X X
X X
11 Process Corriputer X
XW X
X (5) Between 80 and 90 percern g
i 12 RCIC
\\
X XO4) thermal power, and near 100 e
13 HPCI X
X percent core flow j
14 Selected ProcessTemp X
X"I X
(6) Max FW Runout Caoebility and 14 Water Level Ref Leg Temp X
X X
Recirc Pump Runback rrasst
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15 System Empension X
X X
X X
have steady boen completed Tic c.ald EbYdth 17 Core Performance X
X X
X X
X
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18 Steam producten X
m Reactor power between 80 and desseadPebeta may b A
k P4ese64 JacI a
20 Promure Repstator X
X X
X X
X (8) Reactor power between 45 and 21 F eed Sys - Setpoet Changes X
X X
X X
X X
65 percent and 75 and 90 percent w Mgg g g g 21 Feed Sys - Los FW Hestmg XW 21 Feedwater Pump Trip Xts (9) Deleted p, gg ggg
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21 Mae FW Runout Capability X
22 Turbano Vanse Surveillance X tel X" l (10) At mesimum power that will not 3 p g, 23 MSIV FunctionalTest X
XUll J
23 MSiv Full isolaten X
(11) Perform between test conditions e
24 Relief Velwes X, XQOn XQOf X(203 1 and 3 25 Turberie Tno and Load Rejecten X g' XMM L
H 26 Shutdown Outside CRC X
IIII O*'"d 27 Recirculaten Flow Control Xf1*l X 181 1
(13) Ddmed (1 L) hC f be Wd 44 b 28 Recirc - One Puerip Trip X
X 28 RPT Trio - Two Pumps XO91 (14) Between test conditione 2 and 3 28 Racire System Performance X
X X
X h(n8M0f 3
28 Recwc SYS. CMTITATICN O
X (15) Tuh @, within bypass valve caoacity sij ac k P C,ti2 M 30 Loss of Offste Pwr X
(16) Deleted 31 Pipe Veraten X
X X
X X
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29 Racirc Flow Calibration X
X (17) Load rejection 32 RWCU XG33
<tpfed M c709 e 33' RHR Xm yml (18) Between test conditions 5 and 6 34 Drywell and Steam Tunnel Cooiing X
X X
X X
IN b -
g3g3 g 35 Gassous Radweste X
X X
38 SACS *erformance X
X (20) Check SRV operability during 40 Confirmetory InPlaat Test X
X maior scram tests
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